ML13066A318

Indian Point Unit 3 - Draft Operating Exam (Sections a, B, and C) (Folder 2)

ML13066A318
Person / Time
Site:	Indian Point
Issue date:	02/27/2013
From:	D'Antonio J NRC Region 1
To:	Entergy Nuclear Indian Point 3
Jackson D E
References
TAC U01866
Download: ML13066A318 (350)

Text

---

---

Appendix C Job Performance Measure Form ES-C-1 Facility:

I ndian Point 3 Task No: 2000060131 Task Title: Perform a Quadrant Power Tilt Calculation by Hand 1940012125 KIA

Reference:

RO -3.9 Job Performance Measure No: RO Admin 1 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 measure will be Initial

• Plant is at 100% power BOL.

• The Control Room personal computer is unavailable.

Task Standard:

QPTR properly calculated.

Required Materials:

Calculator, GRAPH-NI-2 General

References:

3-S0P-RPC005A, GRAPH-NI-2 Initiating Cue: You are the BOP and You are directed to perform a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of SOP-RPC-005A Time Critical Task: No Validation Time: 45 minutes 1 of 10 Appendix Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/) 1. Performance Step: Obtain correct procedure Standard:

Obtain current revision of 3-S0P-RCP-005A Comment: 2. Performance Step: Review Note before Step 1 Standard:

Reviews Note Comment: Performance Step: ENSURE appropriate meter range for detectors A and B, for each operable NIS Power Range Channel Ensures range meter indication between 1/3 and 2/3 of full scale Comment: Attachment Step 1.0 2 of 10 Performance Information (Denote critical steps with a check mark -/) 4. Performance Record the following current information:

Records the following on Attachment 1

• Date T odays Date

• Time Current Time * % Power Indicated Power Attachment Step 2.0 ...J 5. Performance RECORD UPPER and LOWER detector currents on operable NIS Power Range drawers Candidate demonstrates the ability to obtain readings from the correct meters and records them appropriately in the attachment Cue: Question the Candidate on how to obtain the detector currents.

Provide the Candidate with detector currents for use in the remainder of the JPM Attachment Step 3.0 6. Performance If power range current amp is unavailable This step is Not Applicable Attachment Step 3.1 3 of 10 Performance Information (Denote critical steps with a check mark ...J) ...J 7. Performance Step: Standard:

CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps by full power zero axial offset detector current from GRAPH-NI-2 Enter data and calculate corrected detector current ratios 41 Upper 799/790=1.011 41 Lower 843/850=0.991 42 Upper 818/825=0.991 42 Lower 823/822=1.001 43 Upper 875/890=0.983 43 Lower 873/875=0.998 44 Upper 832/830=1.002 44 Lower 896/910=0.985 Comment: Attachment Step 4 ..J 8. Performance Step: Standard:

DETERMINE both upper and lower Average Normalized Ratios CALCULATE average normalized ratios for Upper detectors:

=41U + 42U + 43U + 44U = 1.011+0.991+0.983+1.003 4 4 = 0.995 CALCULATE average normalized ratios for Lower detectors:

= 41L + 42L + 43L + 44L = 0.991+1.001+0.998+0.985 4 4 = 0.994 Comment: Attachment Step 5 4 of 10 Appendix Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) '" 9. Performance DETERMINE both upper and lower Quadrant Power Tilt as follows Standard:

= Highest Ratio of 41 U + 42U + 43U + 44U = 1.011 Average Ratio 0.997 =1.014 = Highest Ratio of 41 L + 42L + 43L + 44L = 1.001 Average Ratio (Step 6.2) 0.994 = 1.007 Values obtained by the candidate may vary depending on how decimal places they carry. Attachment Step 6.0 10. Performance Step: Record Highest Quadrant Power Tilt calculated Standard:

Records 1.014 Attachment Step 7.0 5 of 10 Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) 11. Performance Step: If Quadrant Power Tilt exceeds 1.02 in either top or bottom of core ... Standard:

Determines QPTR does not exceed 1.02 Comment: Attachment Step 8.0 Terminating Cue: JPM Complete 6 of 10 Appendix C Page 7 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:

Result: SAT or Examiner's signature and date: ___________7 of 10 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• Plant is at 100% power BOL.

• The Control Room personal computer is unavailable.

Initiating Cue: You are the BOP and You are directed to perform a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of SOP-RPC-005A Appendix C Initial Conditions Form Actual Detector Currents I Channel Top Bottom I 41 799 843 42 818 823 i 43 875 873 I 44 832 896 I Appendix C Initial Conditions Form ES-C-1 3-GRAPH-NI-2 Rev. NIS FULL POWER DETECTOR CURRENTS Cycle (Values updated based on 17C20 flux map at 99.9% RTP) FACE PLATE CURRENT Channel TOP OTTOM N41 790 N42 825 N43 890 N44 830 IR DETECTOR CURRENT LIMITS FOR USE IN 3-POP-1.3 N35 Current limit (Amps) N36 Current limit CAmps) 4%RTP 0.85 E-05 1.72 8%RTP 1.70 E-05 3.44 Written By: Reviewed By: Signature Approved By Signature Effective Date: Today' s Date

• Procedure Use Is: Control Copy: ____

if Continuous Nuclear Northeast o Reference Effective Date: ___ o Information Page 1 of 13 3-S0P-RPC-OOSA, Revision:

S QUADRANT POWER TILT CALCULATIONS Approved By: Team 3D Procedure Owner EDITORIAL No: 3-S0P-RPC-00SA Rev:S QUADRANT POWER TILT CALCULATIONS Page 2 of 13 REVISION

SUMMARY

(Page 1 of 2) REASON FOR REVISION Updated to eliminate poor practices and ensure procedure contains proper level of detail.

SUMMARY

OF CHANGES Moved and revised former Step 1.2, of Purpose, to Step 2.2.1 of P&Ls, General Information (Editorial 4.6.13). Moved and revised former Step 1.3, of Purpose, to Step 2.2.2 of P&Ls, General Information (Editorial 4.6.13). Deleted former P&L 2.1 regarding RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors.

Other methods exist to ensure requirements are met (Editorial 4.6.12). Split Section 2, Precautions and Limitations, into 2 parts: 2.1, Precautions and Limitations and 2.2, General Information (Editorial 4.6.10). Added P&L 2.1.1 regarding use of uncorrected detector outputs to be consistent with Unit 2 procedure (Editorial 4.6.11). Added P&L 2.2.3 regarding short term Tilt spikes with alarm actuation following ReS boron changes to be consistent with Unit 2 procedure (Editorial 4.6.11). Added "IF Reactor Power is less than or equal to 7S%, THEN" to Step 3.1 to clarify SR 3.2.4.1 (Editorial 4.6.13). Deleted former Step 3.2 regarding reactor power being greater than SO%. Per Reactor Engineering, QPTR can be performed at lower power, but becomes less accurate (Editorial 4.6.12). Added Step 3.2 "IF Reactor Power is greater than 7S%, THEN VERIFY all four NIS channel upper and lower detectors are in service" to clarify SR 3.2.4.1 (Editorial 4.6.11) Added Note prior to Step 4.1 regarding normalization factors not being available following refueling or detector maintenance (Editorial 4.6.11). Split Section 4.1 into two parts: 4.1, Manual Quadrant Power Tilt Calculation and 4.2, Computer Network Program Quadrant Power Tilt Calculation (Editorial 4.6.14).

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 3 of 13 (Page 2 of 2) Changed Step 4.2.8 from "SELECT" to "ENTER" and deleted bullet regarding clicking "OK" and appropriate option button as there are no 'select' options (Editorial 4.6.13). Added 2 bullets to Note prior to Step 4.2.8 to clarify when 3 or 4 operable NIS Power Range channels are used (Editorial 4.6.11). Deleted former Step 4.1.13 regarding performing RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors.

Other methods exist to ensure requirements are met (Editorial 4.6.12). Deleted former Steps 4.1.14.2,4.1.14.3 and 4.1.14.4 as these are all included in Tech Spec 3.2.4 (Editorial 4.6.12). Added bullet to Step 4.2.13 to enter calculated Quadrant Power Tilt in the Narrative Log (Editorial 4.6.11). Added Reference 5.2.2, SR 3.2.4.1 (Editorial 4.6.4). Deleted former Reference 5.3.1, RA-11.1, as it is no longer mentioned in procedure (Editorial 4.6.12). Added Reference 5.6.1, 0-NF-303, Core Quadrant Power Balance as an Interface Document (Editorial 4.6.11). Added Reference

5.7.1 UFSAR

Section 7.6.2 (Editorial 4.6.11 ). Deleted former Step 4.0 of Attachment 1 regarding performing RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors.

Other methods exist to ensure requirements are met (Editorial 4.6.12). Added "when Reactor Power is less than or equal to 75%, then 3 NIS power range channels can be used" to Note in Step 5 of Attachment 1 to clarify when 3 operable NIS Power Range channels can be used (Editorial 4.6.13). Added bullets to Step 8.0 of Attachment 1 to verify requirements of LCO 3.2.4 are met, notify CRS and SM and to enter QPTR in the Narrative log (Editorial 4.6.11). Changed Step 10.0 of Attachment 1 to forward Attachment 1 to Operations Staff to simplify the action. Placing in Operations Log binder has the same result of forwarding to Operations Staff (Editorial 4.6.13).

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 4 of 13 TABLE OF CONTENTS Section Title Page 1.0 PURPOSE ......................................................................................................................... 2.0 PRECAUTIONS AND LIMITATIONS

................................................................................. 3.0 PREREQUiSiTES

.............................................................................................................. 4.0 PROCEDURE

....................................................................................................................4.1 Manual Quadrant Power Tilt Calculation

.................................................................... 4.2 Computer Network Program Quadrant Power Tilt Calculation

...................................

5.0 REFERENCES

..................................................................................................................6.0 RECORDS AND DOCUMENTATION

................................................................................

ATTACHMENT 1 MANUAL QUADRANT POWER TILT CALCULATION

................................

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT I Page 5 of PURPOSE This procedure provides guidance for the preparation of quadrant power tilt calculations in accordance with Technical Specification surveillance requirement SR 3.2.4.1. PRECAUTIONS AND LIMITATIONS Precautions and Limitations Uncorrected detector outputs SHALL NOT be used to calculate quadrant power tilt because they do NOT represent relative core power in their associated quadrant. General Information WHEN in MODE 1 with greater than 50 percent of rated thermal power AND quadrant power tilt exceeds 1.02. THEN VERIFY QPTR is within limit by calculation once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (Reference 5.2.1} WHEN in MODE 1 with greater than 50 percent of rated thermal power AND either one upper OR lower quadrant power tilt alarm monitors are inoperable.

THEN verify QPTR is within limit by calculation once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND after load change greater than 10 percent of rated power. (Reference 5.2.3} Short term Quadrant Power Tilt calculation spiking with possible Plant Computer System alarm actuation can occur immediately following Reactor Coolant System (RCS) boron changes. These short term spikes, (approximately five minutes duration), should not be considered significant.

as they are transitory in nature. PREREQUISITES IF Reactor Power is less than or equal to 75%, THEN VERIFY a Minimum of three NIS channel upper and lower detectors are in service. (Reference 5.2.2) IF Reactor Power is greater than 75%, THEN VERIFY all four NIS channel upper and lower detectors are in service.

! No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS I Page 6 of 13 4.0 PROCEDURE NOTE Following refueling or detector maintenance, prior to performance of initial at-power incore flux mapping operations, NIS detector current output normalization factors will not be available.

During this period, NIS detector current outputs must be logged as required below, but quadrant tilt calculations cannot be performed.

4.1 Manual

Quadrant Power Tilt Calculation IF desired to perform a manual calculation, THEN GO TO ATIACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION.

4.2 Computer

Network Program Quadrant Power Tilt Calculation NOTE A detector current meter range should be selected which places meter indication between 1/3 and 2/3 offull scale. VERIFY appropriate meter range is selected for detectors A and B for each operable NIS channel. RECORD the individual upper and lower power range detector currents indicated on each operable NIS Power Range drawer in the following table: TABLE UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT 41 42 43 44 No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER rllT Page 7 of WARNING Electrical shock hazard inside drawer. IF a power range detector current amp reading is unavailable, THEN: CONTACT I&C to obtain a DVM current reading for the appropriate drawer. RECORD DVM reading(s) in the Table provided in Step 4.2.2. ACCESS the QPTR Program (\\ipcfsetsp002\OPERATIONS\OPS General\!

P3\Software\Unit 3\QPTR\QPTR.exe). IF the network is unavailable AND CCR computer is operational, THEN: OBTAIN the QPTR Program CD from Shift Manager's office. INSERT CD in a CCR computer AND OPEN QPTR Program. CLICK the "Click Here to Start" button to retrieve 100% NIS currents from 3-Graph-NI-2. COMPARE the latest NIS currents against the 3-Graph-NI-2 values. IF the 100% NIS currents do not match 3-Graph-NI-2.

THEN CLICK the "No" button AND ENTER 100% currents and 3-Graph-NI-2 revision number in the text boxes when prompted. IF the 100% NIS currents match the latest revision of 3-Graph-NI-2, THEN click the "Yes" button. WHEN prompted, THEN ENTER today's date, the current time and the current % power.

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 8 of 13 NOTE This program can be used for either 3 or 4 operable NIS Power Range channels. Three operable NIS Power Range channels can be used when Reactor Power less than or equal to 75%. (Reference All four operable NIS Power Range channels are required when Reactor Power greater than ENTER the correct number of operable NIS Power Range channels. ENTER appropriate NIS information from Table of Step 4.2.2 in the white text boxes. IE a power range channel that is out of service, THEN ENTER "0" for the applicable channel in the white text boxes. CLICK on the CALCULATE QPTR button to show the current QPTR. CLICK on the PRINT RESULTS button to obtain computer printout of the quadrant power tilt calculation. IE Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following:

• VERIFY requirements of LCO 3.2.4 are met.

• NOTIFY CRS AND SM.

• ENTER calculated Quadrant Power Tilt in the Narrative Log. WHEN QPTR calculation program is no longer required, THEN CLICK "Quit Program". OBTAIN CRS and SM signatures for the completed QPTR printout. PLACE completed QPTR computer printout in Operations Log binder.

I I No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS I Page 9 of 13 Commitment Technical LCO 3.2.4 Action SR TRO 3.2.A Action Development Historical Development 3 PT-W022 , Quadrant Power Tilt Interface O-NF-303, Core Quadrant Power 3-Graph-NI-2, NIS Full Power Detector UFSAR 5,7.1 Section RECORDS AND The following required records resulting from this procedure controlled and maintained in accordance with the IP3 Records

• Attachment 1, Manual Quadrant Power Tilt Calculation Sheet

• Computer-generated printout of Quadrant Power Tilt Calculation 6,2 Documentation The following documentation is required to be controlled or maintained accordance with the IPEC Records Retention

• None

---

No: 3-S0P-RPC-OOSA Rev:S QUADRANT POWER TILT Page 10 of ATIACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 1 of 4) NOTE A detector current meter range should be selected which places meter between 1/3 and 2/3 of full ENSURE appropriate meter range is selected for detectors A and B, for each operable NIS Power Range channel. RECORD the following current information:

Datec_____ Time________ % Power RECORD individual upper and lower Power Range detector currents indicated on each operable NIS Power Range drawer in the following Table 1: NOTE Enter "0", if one power range channel is out of service. POWER RANGE CHANNEL 41 42 43 44 TABLE 1 UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TIL T Page 11 of ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 2 of 4) WARNING Electrical shock hazard inside drawer. IF power range current amp is CONTACT I&C to obtain a DVM current reading for the appropriate drawer. RECORD DVM reading(s) in Table 1 of Step 3.0. CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps recorded in Table 1 of Step 3.0 by full power zero axial offset detector current obtained from last incore/excore calibration (3-Graph-NI-2, NIS Full Power Detector Currents):

Indicated 3-Graph-NI-2 3-Graph-NI-2 Normalized Detector Current Current Ratio Current Current Ratio 41 Upper T = 41 = 42 Upper + = 42 Lower + = 43 Upper T = 43 Lower + = 44 Upper + = 44 Lower + =

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TIL T CALCULATIONS Page 12 of 13 ATTACHMENT MANUAL QUADRANT POWER TILT (Page 3 of DETERMINE both upper and lower Average Normalized Ratios as follows: NOTE When Reactor Power is less than or equal to 75%. then 3 NIS power range channels can be used. (Reference 5.2.2) If ONLY 3 NIS power range channels are in service, then "0" is entered for the inoperable channel, AND the sum of the currents is divided by 3. CALCULATE average normalized ratio for Upper 41U + 42U + 43U + = == 3* or 4*

• See note above CALCULATE average normalized ratio for Lower 41L + 42L + 43L + = = 3* or 4*

• See note above previous sub-step NOTE Upper Quadrant = Highest Normalized Ratio for Upper Detector (Step Power Tilt Average Normalized Ratio for Upper Detector (Step Lower Quadrant = Highest Normalized Ratio for Lower Detector (Step Power Tilt Average Normalized Ratio for Lower Detector (Step DETERMINE both upper and lower Quadrant Power Tilt as follows: CALCULATE Quadrant Power Tilt for Upper

= Highest Ratio of 41 U, 42U, 43U, or 44U =__= Average Ratio (Step 5.1) CALCULATE Quadrant Power Tilt for Lower Highest Ratio of 41 L, 42L, 43L, or 44L =___ = Average Ratio (Step 5.2)

No: 3-S0P-RPC-OOSA Rev:S QUADRANT POWER TILT Page 13 of ATIACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 4 of 4) RECORD highest Quadrant Power Tilt calculated in Steps 6.1 OR 6.2: Highest Quadrant Power Tilt____________

_ IF Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following: VERIFY requirements of LCO 3.2.4 are met NOTIFY CRS AND SM ENTER calculated Quadrant Power Tilt in the Narrative Log REVIEW Attachment 1 for satisfactory completion:

I Control Room Supervisor Date I Time I Shift Manager Date I Time WHEN complete, THEN FORWARD this Quality Record to the Operations Department Records Custodian.

Date

---

Appendix Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Task No: 0040270131 Task Title: Perform Deborating Demineralizer In-Service Time Calculation 2.1.25 Job Performance Measure KIA

Reference:

RO -3.9 No: ROAdmin 2 NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance x Classroom x

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: CVCS is aligned for normal operation RCS filter is in service The demineralizer has been final rinsed Reactor Power is 100% Control Bank D is at 228 steps Current Tavg is 568°F Desired Tavg 569°F ITC -33.4 pcmrF Letdown Flow is 84 gpm Current Boron Concentration is 98 ppm Deborating Bed 31 is in service Deborating Demineralizer effluent is 14 ppm Sampled 0100 today. The SM had determined that the Deborating Demin will be used to reduce RCS boron concentration.

Task Standard:

In-Service Time properly calculated.

Required Materials:

Calculator Procedure 1 of 6 Appendix C Job Performance Measure Form ES-C-1 General

References:

3-S0P-CVCS-004 Initiating Cue: You are the spare RO and the CRS has directed you to determine the Deborating Demineralizer In-Service Time using 3-S0P-CVCS-004 step 4.3.4. Time Critical Task: No Validation Time: 45 minutes 20f6 Appendix Page 3 Form Performance Information (Denote critical steps with a check mark -.J) 1. Performance Step: Determine RCS has not been borated to cold shutdown +100 ppm and Rx Trip Breakers are Open Standard:

Given in Initial Conditions Comment: Procedure Step 4.3.4.1 Performance Step: Determine RCS Boron Concentration is > 3ppm and Rx Power is > 99%.

Given in Initial Conditions Comment Procedure Step 4.3.4.2 "3. Performance Calculate the change in Tavg on Attachment 1

A Tavg = TF -TI A Tavg = 569°F -568°F Comment: Procedure Step 4.3.4.3 "4. Performance Calculate the change in RCS Boron Concentration for the change in Tavg on Attachment 1 A B =A Tavg

• ITC

• IBW A B = 1°F * -33.4 pcm/oF*-O.1074 ppm/pcm A B =22.1 ppm Comment: Procedure Step 4.3.4.4 30f6 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark "5. Performance Step: Calculate Boron Efficiency for selected deborating demineralizer Standard:

BE :: 1 -(BO/BI) BE =1 -(14/98) BE = .86 Comment: Procedure Step 4.3.1.1 " 6. Performance Step: Calculate G -gallons of water using Graph CVCS-3 Standard:

From Nomograph

-13,500 +/-500 gallons Comment: Procedure Step 4.3.4.5 " 7. Performance Step: Calculate the Deborating Demineralizer in-service time Standard:

T =G I (LF .. BE) T :: 13500 gallons I (84 gallons/min" 0.86) T = 186.8 minutes (179 to 193 minutes) Comment: Procedure Step 4.3.4.5 Terminating Cue: JPM Complete 4of6 Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Result: SAT or Examiner's signature and date: __________50f6 Appendix C Initial Conditions Form ES-C-1 Initial Conditions: CVCS is aligned for normal operation RCS filter is in service The demineralizer has been final rinsed Reactor Power is 100% Control Bank D is at 228 steps Current Tavg is 568°F Desired Tavg 569°F ITC -33.4 pcmfOF Letdown Flow is 84 gpm Current Boron Concentration is 98 ppm Deborating Bed 31 is in service Deborating Demineralizer effluent is 14 ppm Sampled 0100 today. The SM had determined that the Deborating Demin will be used to reduce RCS boron concentration.

Initiating Cue: You are the spare RO and the CRS has directed you to determine the Deborating Demineralizer In-Service Time using 3-S0P-CVCS-004 step 4.3.4.

PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 19 of 37 CAUTION When more than one unsaturated demineralizer is placed in service at the same then the margin to cold shutdown boron must be evaluated by

4.3.4 Determining

Deborating Demineralizer In-Service Time IF RCS has been borated to cold shutdown +100 ppm boron concentration AND the Reactor Trip Breakers are OPEN, THEN GO TO Step 4.3.5 to place Deborating Demineralizer(s) in service as required (assist in crud burst cleanup). IF RCS Boron Concentration is less that 3 PPM AND Reactor Power is less than 99%, THEN GO TO Step 4.3.5 to place Deborating Demineralizer in service as required.

NOTE This method is intended for use at approximately 100% power due to the basis Attachment 2, Inverse Boron Worth vs Boron CALCULATE the change in Tavg required on Attachment 1 as follows: A Tavg = TF -TI, where A Tavg = Required change in Tavg (OF) TF= Final Tavg(OF) TI = Initial Tavg(OF)

PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 20 of 37 CALCULATE the change in RCS Boron concentration for the change in Tavg on Attachment 1 as follows: B =Tavg

• ITC

• IBW, where L\ B = Change in RCS Boron Concentration (ppm) Tavg =Required change in Tavg (OF) ITC = At Power Isothermal Temperature Coefficient for the initial Tavg(pcm/oF), from Graph RV-5B IBW = Inverse Boron Worth (ppm/pcm) for the initial RCS Boron concentration, from Attachment 2, Inverse Boron Worth VS Boron Concentration CALCULATE the Deborating Demineralizer in-service time on Attachment 1 as follows: T =G / (LF

• BE), where T =required Deborating Demineralizer in-service time (Min) G =Amount of dilution water required for the change in boron concentration (gals),from Graph CVCS-3, (Dilution Nomograph for Hot ReS 580°F) or CCR computer.

LF =Letdown Flow (gpm), from FI-134 BE =Boron Efficiency for the selected Deborating Demineralizer PLACE completed Attachment 1, Deborating Demineralizer In-service Time Calculations, in Daily Log Binder for Operations Staff to review and file.

PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 36 of 37 ATTACHMENT 1 DEBORATING DEMINERALIZER IN-SERVICE TIME CALCULATIONS (Page 1 of 1) Required change in Tavg: = 4.3.4.4 Change in RCS Boron concentration:

= *

• A B (ppm) IBW (ppm/pcm) 4.3.1.1 Boron Efficiency for Deborating Demineralizer:

Bed No. Sample Time Sample Date ________

______________________ , _________________________BE BO (ppm) BI (ppm) 4.3.4.5 Deborating Demineralizer in-service time: --------= -----, ('-----------------

• ------------')

T (min) G (gal) LF (gpm) BE Rev: 25 No: 3-S0P-CVCS-004 PLACING THE CVCS DEMINERALIZERS IN OR OUT OF Page: 37 of 37 ATIACHMENT2 INVERSE BORON WORTH VS BORON CONCENTRATION (Page 1 of 1) -0.105 -0.106 I I I .ti-.J I I I I I I I I J ... LL_ I I 1 I , I I I I .1 ..1 _ l I I I I I I I I II.LI.. I I I I I I I I I I I I I I I I LL.L J. rb o m c I I 1 I I'_I. I I I I I I I 1 ..1.1 I I I I I I I I . I I I I I I I I I I I I I I I 1 I I I I I I I I I 1.1. I I I 1 I I I I I t 1 I _I I I I I I I I I I I I I I I I I I I I I I I 1 I I. I I

• I t I I I 1II1 111111111\111111111111111111 1'1' III1 IIII IIII 1111 II1I III ..LI.LL I '.1 I. ...Ll.LI_ J_.J_I.J ...*L.LLL LLL.I . .oLt I II1I III' 'III I1II 1.11 IIII III,_LL1J_ J_L NOTE: This graph for use at Hot Full Power .L I I I I I I All ROds Out conditions only. II I I t I I I -r-t**t-t-"I-l'*:}*I-:**:>i-rl--t-;-:-t-l-rt-l-t-l-t

..t-:. t-I> I" 1-1": 1111 I1II Jill IIII 11ft IIII III1 I I_I.. I J _L.I .* 1. LLL _J.Li..! ..l. LLI .1. I I. I ,_It.1 I .....'1 IIII IIJI IIII IIII IIII IIII I I I I I I I I I I I I I I I I I l I I I I I I III III "ll IIII III III III IIII IIII I I I I .1.1. I ..LLJ I 1..1 t. -I. 1.1 I. III I III III II1I I1II 11\ I III III I11I IIII I I I I I L I I .t J I I I I. t I I I III III III IIII 1III IIII III1 III II 11II IIII IIII .*1.1 LI . .1.1.1 1_ "L.LI.I .I..I.L I. 11.1 I IIII III II 1111'111 IIII IIII1III II 111 III1 1III . L I 1 I J I I. J. J .1. 1..1 . _ _ J I I I _ I I .l. 1.1 I III1 IIII IIII , I IIII IIII IIII IIII 1III III IIII IIII III IIII I f I I I1II IIII I I I I 1.1 f I. 11.1 I. .t. LI. I .1 t IIII1III II I I I I I IIII 11l.1 II I .1 I lilt IIII I I I I I I I I II I I I I

'I I I I I I I I I IIII 'III I I I I I I I I1111 1111 I I I I I I II1I IIII II I I I I I I I IIIII IIII I I I I I .ltll 111..1 II I J I I I , I I 1111 Iftl II I I I I I I IIII IIII II I I I I I I I I I I I I _.L ... .1._ .....I---L-l. 80 90 100 10 20 30 40 50 60 70 Boron Concentration (PPM)

Unit 3 Rev. 0

• DILUTION NOMOGRAPH 10 -FO R 10 HOT ReS 20 30 itO 50 60 70 50 .......100 500 800 200 .,.1000 300 10 *2000 500 5000 100 10,000 1000 20,000 2000 1000 50,000 2000 100,000 3000 PPM BOROH PPM BORON It( COOLANT DILUTION WATER Reviewed By: K._ . Approved By . J_ It.!.. -.A;t:/cvcs-3 page 3 of 9 .. Section 4

---

---

---

Appendix Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point Task No: 2000390131 Task Title: Prepare a Tagout 1940012213 Job Performance Measure KIA

Reference:

RO -4.1 No: ROAdmin 3 NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance x Classroom x

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 in Cold Shutdown with no fuel in the reactor The eSOMS Clearance Module is unavailable. The Shift Manager has determined that 33 Charging Pump must be tagged out for seal replacement. Clearance Number is 3C20 Tagout Number is CH-038. No deficiencies exist on valves identified in tagout boundary The shift manager has waived the requirement for double valve protection. Single Valve protection is adequate for this tagout. Task Standard:

Manual Tagout Complete and ready for review Required Materials:

None General

References:

EN-OP-102, Protective and Caution Tagging 3-COL-CVCS-001 Chemical and Volume Control System EN-OP-102-1, Protective and Caution Tagging Forms &Checklists 9321-F-27363 Flow Diagram Chemical and volume Control System Sheet 1 1 of 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: You are a spare reactor operator and the SM has directed you to prepare a manual tagout for 33 Charging Pump using EN-OP-102 and 102-01. Time Critical Task: No Validation Time: 45 minutes 20f9 Performance Information (Denote critical steps with a check mark 1. Performance Step: Obtain Correct Procedure Standard:

Obtains EN-OP-102 and EN-OP-102-01 Comment: Performance Step: Ensure requirement of Attachments 9.1 and 9.2 of OP-102 are followed Review Attachment 9.1 and 9.2 CommentStep Procedure Step 5.3 [1] 3. Performance Review Scope of Work Tagout Required for emergent work. Given in Initial Conditions Comment: Procedure Step 5.3 [2] Performance Step: Determine Safe Work Boundary for 33 Charging Pump Seal Replacement Review Plant Prints 9321-F-27363 Comment: Procedure Step 5.3 [2] (g) 3 of 9 Appendix9

__________

P_a-"'9!-e_4

__________

Fo_r_m_E_S-_C_-_1 Performance Information (Denote critical steps with a check mark ...J) Performance Step: Boundary Valves should be reviewed for outstanding deficiencies Standard:

No deficiencies exist on valves identified in tagout boundary -Given in Initial Contitions CUE: No deficiencies exist on valves identified in tagout boundary Comment: Procedure Step 5.3 [3] 6. Performance Step: Standard:

Comment: Utilizing the Isolation Boundaries, Prepare the tag out For each tag include:

• Tag Type

• Component/Equipment Number

• Component/Equipment Name

• Component/Equipment Location

• Component Hang and Restoration Position

• Tagout Hang Sequence See Attached Answer Key 4of9 Appendix PageS Form ES-C-1 Performance Information (Denote critical steps with a check mark Key Elements From Attachment

9.2 Tagging

Sequence All Tagouts require tags to be hung and cleared in the order specified on the Tag Hang sheet or Tags To Be Removed sheet. When no definitive order is required for certain components of a Tagout, the Operations Supervisor may specify a given order number for multiple components (e.g., multiple components listed on the Tagout may be given order number "5" when their sequence relative to each other is not important). Recommended tagging order for pumps A. Control switch B. Breaker for main power C. Breakers for auxiliary power (motor heater, oil pumps, etc.) D. Discharge valve E. Suction valve F. Other components within scope of Tagout Terminating Cue: JPM Complete S of 9

---

---

---

ATTACHMENT 9.3 T AGOUT TAGS SHEET CLEARANCE:

3C20 MANUAL CH-038 TAGOUT: _______ 3 4 5 6 7 8 9 10 11 Tag Equipment Type Equipment Description Equipment Location 133 Charging Pump Danger Switch 133 Charging Pump Danger Control Fuses Room Bus 5A 133 Charging Pump Danger Room Bus 5A 33 Charging Pump Outlet solation Danger ;33 Charging Pump Cell pH-238 33 Charging Pump Outlet solation to Seal Injection Danger 33 Charging Pump Cell vH-409 33 Charging Pump Recirculation Isolation Danger 33 Charging Pump Cell CH-281 33 Charging Pump Relief and Recirculation Line Outlet Isolation Danger 33 Charging Pump Cell CH-284 33 Charging Pump Inlet solation Danger 33 Charging Pump Cell CH-418 33 Charging Pump Suction Stabilizer Drain Danger P3 Charging Pump Cell 33 Charging Pump Suction ine Drain Danger P3 Charging Pump Cell PH-419 33 Charging Pump Suction Stabilizer Vent Cap Danger ;33Charging Pump Cell 4 5 6 7 8 9 10 11 Pull to Racked Closed Closed Closed Closed Closed 1----Open Open Cap Removed Place. Place. Rest. 1st Rest. 2nd Placementl 1st Verif 2nd Verif Rest. Restoration Verif Verif Removal

__ DatefTime Seq. Configuration DatefTime DatefTime TaflNotes CRITICAL Auto Installed/On CRITICAL Racked In ---------------1---CRITICAL Open CRITICAL Open --------r--------CRITICAL Open Open CRITICAL Open Closed Closed CRITICAL Cap Installed

-6of9 I ATTACHMENT

9.3 TAGOUT

TAGS SHEET 12 Danger CH-419 33 Charging Pump Suction Stabilizer Vent 12 Open Closed 13 Danger 33 Pump Cell CH-103 33 Charging Pump Outlet Vent Cap 13 Cap Removed CRITICAL Cap Installed 14 33 Charging Pump Cell ...H-103 33 Charging Pump Outlet Vent Danger Pump Cell 14 Open Closed I I 7 of 9 Appendix C Initial Conditions 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:

Result: SAT or UNSA Examiner's signature and date: ___________

Appendix C Initial Conditions Form ES-C-1 Initial Conditions: The unit is in Cold Shutdown with no fuel in the reactor The eSOMS Clearance Module is unavailable. The Shift Manager has determined that 33 Charging Pump must be tagged out for seal replacement. Clearance Number is 3C20 Tagout Number is CH-038. No deficiencies exist on valves identified in tag out boundary The shift manager has waived the requirement for double valve protection. Single Valve protection is adequate for this tagout. Initiating Cue: You are a spare reactor operator and the SM has directed you to prepare a manual tagout for 33 Charging Pump using EN-OP-102 and EN-OP-102-01.

r CHEMICAL AND VOLUME CONTROL Rev: 27] SYSTEM i Page 27 of 41 Des. Oper Actual Pos. Pos.

Initial IV 2.12 Charging Pumps 55' Elev. -PAS 2.12.1 Charging Pumps Local Control Station 31 Charging Pump Control Switch Remote 32 Charging Pump Control Switch Remote 33 Charging Pump Control Switch Remote -..*CH-AOV-200A 45 GPM Letdown Orifice Control Switch Auto AR CH-AOV-200B 75 GPM Letdown Orifice Control Switch Auto AR CH-AOV-200C 75 GPM Letdown Orifice Control Switch Auto AR 0 PI-142 Vent (next to charging pumps stabilizer heater panel) Shut 2.12.2 31 Charging Pump Cell CH-1175B 31 Charging Pump Suction Line Drain Shut CH-278 31 Charging Pump Inlet Isolation Open CH-273 31 Charging Pump Relief and Recirculation Line Outlet Isolation LO CH-230 31 Charging Pump Outlet Isolation Open CH-232 31 Charging Pump Outlet Isolation to Seal Injection Open NED-275 31 Charging Pump Seal Tank Overflow Isolation Open CH-407 31 Charging Pump Recirculation Isolation Shut CH-1 31 Charging Pump Strainer DIP Hi Side Isolation Shut Capped CH-2 31 Charging Pump Strainer DIP Low Side Isolation Shut Capped

---I 'No:3-COL-CVCS-001 Rev: 27 ICHEMICAL AND VOLUME CONTROL SYSTEM Page 28 of 41 L--_______________________________________________

.__________

__I 2.12 CH-101 CH-412 CH-413 CH-414 (CONTINUED) 31 Charging Pump Outlet Vent 31 Charging Pump Suction Stabilizer Drain 31 Charging Pump Suction Stabilizer Vent 31 Charging Pump Suction Stabilizer Drain Line Vent 31 Charging Pump Transfer Switch 31 & 32 Charging Pumps Disconnect Switch 2.12.3 32 Charging Pump Cell CH-288 RWST to Charging Pumps Suction Isolation CH-289 Charging Pump Suction Header Isolation CH-1175C 32 Charging Pump Suction Line Drain CH-283 32 Charging Pump Inlet Isolation CH-276 32 Charging Pump Relief and Recirculation Line Outlet Isolation CH-235 32 Charging Pump Outlet Isolation CH-233 32 Charging Pump Outlet Isolation to Seal Injection NED-279 32 Charging Pump Seal Tank Overflow Isolation CH-408 32 Charging Pump Recirculation Isolation CH-3 32 Charging Pump Strainer DIP Hi Side Isolation CH-4 32 Charging Pump Strainer DIP Low Side Isolation Des. Oper Actual Pos. Pos. Initial IV Shut Capped ___ Shut Shut Capped ____ Shut Capped ____ Normal Locked Locked Off Shut Open Open Open Shut Shut Capped Shut Capped CHEMICAL AND VOLUME 2.12 (CONTINUED)

CH-102 32 Charging Pump Outlet Vent CH-415 32 Charging Pump Suction Stabilizer Drain CH416 32 Charging Pump Suction Stabilizer Vent CH-417 32 Charging Pump Suction Stabilizer Drain Line Vent 32 Charging Pump Transfer Switch 2.12.4 33 Charging Pump Cell CH-113 Charging Pumps Discharge Header Vent CH-1175D 33 Charging Pump Suction Line Drain CH-284 33 Charging Pump Inlet Isolation CH-281 33 Charging Pump Relief and Recirculation Line Outlet Isolation CH-236 33 Charging Pump Outlet Isolation CH-238 33 Charging Pump Outlet Isolation to Seal Injection NED-280 33 Charging Pump Seal Tank Overflow Isolation CH-409 33 Charging Pump Recirculation Isolation CH-5 33 Charging Pump Strainer DIP Hi Side Isolation CH-6 33 Charging Pump Strainer DIP Low Side Isolation CH-103 33 Charging Pump Outlet Vent No:3-COL-CVCS-001 Rev: 27 Page 29 of 41 Des. Oper Pos. Actual Pos. Initial IV Shut Capped Shut Shut Capped Shut Capped Normal Locked Shut Capped Shut Open LO Open Open Open Shut Shut Capped Shut Capped Shut Capped No: 3-COL-CVCS-001 Rev: 27 CHEMICAL AND VOLUME CONTROL 2.12 (CONTINUED)

CH-418 CH-419 33 Charging Pump Suction Stabilizer Drain 33 Charging Pump Suction Stabilizer Vent CH-420 33 Charging Pump Suction Stabilizer Drain Line Vent CH-199 Emergency Boration Line Drain (in overhead)

Page 30 of 41 Des. Oper Actual Pos. Pos.

Initial IV Shut Shut Capped Shut Capped Shut Capped 2.12.5 Charging Pump Cells Passage Way CH-229 0 PT-142 & PI-142 Root Isolation PT-142 & PI-142 Isolation 2.13 Boric Acid Transfer 55' Elev. -PAB 2.13.1 31 Boric Acid Transfer Pump CH-376 CH-363 CH-367A CH-364 CH-360 Boric Acid Batch Tank Outlet Isolation 31 Boric Acid Transfer Pump Primary Water Supply Isolation 31 Boric Acid Transfer Pump Batching Tank Supply Isolation 31 Boric Acid Transfer Pump Suction Isolation 31 Boric Acid Transfer Pump Discharge Isolation to 31 Boric Acid Filter CH-361 CH-355A 31 Boric Acid Transfer Pump Discharge Isolation to 31 Boric Acid Storage Tank PI-190A Isolation Shut Shut Shut Open AR ATTACHMENT 9.3 T AGOUT TAGS SHEET CLEARANCE:

_MANUAL,_____ TAGOUT: __________ ...Tag Tag Equipment Place. Rest. 1st Rest. 2nd PlacemenU Serial Type Equipment Description Place. Placement 1st Verif 2nd Venf Rest. Restoration Verif Verif Removal No.'-.__. Equip!T1ent Location p3 Charging Pump Seq. Configuration Dateffime Dateffime Seq. Configuration Dateffime Tag Notes Pullout 1 Danger pontrol Switch 1 Or CRITICAL Auto Pull to Lock r----..p3 Charging Pump 2 Danger Control Fuses i, Removed/Off Installed/On I _

Room Bus 5A p3 Charging Pump 3 Danger 3 Racked Out CRITICAL Racked In !480V Room Bus 5A _.,...*... .. r----. _. .. ,",H-236 33 Charging Pump Outlet 4 Danger solation 4 Closed CRITICAL Open ChlilrgingPump Cell r---H-238 33 Charging Pump Outlet _. ..5 Danger solation to Seal Injection 5 Closed CRITICAL Open Charging Pump Cell _. -

33 Charging Pump 6 Danger Isolation 6 Closed CRITICAL Open P3 Charging Pump Cell _. ._. ....",H-281 33 Charging Pump Relief and 7 Danger Une Outlet Isolation 7 Closed Open -Charging Pump Cell ,

33 Charging Pump Inlet 8 Danger solation 8 Closed CRITICAL Open P3 Charging Pump _. -_.

33 Charging Pump Suction 9 Danger Drain 9 Open Closed [10 Danger P3 Charging Pump Cell 33 Charging Pump Suction ine Drain 10 Open Closed -..p3 CharginQ Pump Cell r---H-419 33 Charging Pump Suction 11 Danger Stabilizer Vent Cap 11 Cap Removed CRITICAL Cap Installed P3 Charging Pump Cell -_. ..

---

---

---

ATTACHMENT

9.3 TAGOUT

TAGS SHEET ",H-419 33 Charging Pump Stabilizer 12 Danger 12 Open Closed P3 Charging Pump 03 33 Charging Pump Outlet 13 Danger 13 Cap Removed CRITICAL Cap Installed p3 Charging Pump Cell 33 Charging PumpOlitletVEmt 14 Danger 14 Open Closed tn Charaina Puma Cell o OJ y<< .., 'Z 3 J r-IT <I'" >; vl A 'i '" -, w W. (L IX! 0 0 i '" ",0 "vo u :::> '" Z d z 3'?w ": w <iii: '" d z 3c5i75 Le> Z h (,'I:;JO .... U .... l"ID 5 '" rJ

Ii0...):.£", ¥ ..... w z :L" .... WO

'-' 1 ,2:

e i ce--0 ct @ " f I 0 .;., I : z , 1 ' ';0 I ; I "' ....:::: o o

---

---

---

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point Task No: 2000130131 Task Title: Prepare a VC Pressure Relief Release Permit 1940012311 Job Performance Measure ROAdmin 4 KIA

Reference:

-3.8 No: Examinee:

NRC Examiner:

Facility Evaluator:

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

Initial Conditions:

1. The Unit is operating at 100% power. 2. All radiation monitors are operable.

3. VC Pressure is 1.5 psig

• Permit Number 120204

• Radiation Monitor Data: o R-12 Current Reading 7.170 E-7 I-ICi/cc o R-12 Current Alarm 1.5 E-6 I-ICi/cc o R-14 Current Reading 9.948E-7I-1Ci/cc o R-14 Current Alarm 1.5E-5I-1 Ci/cc o R-15 Current Reading 1.32 E-6 I-ICi/cc o R-27 Current Reading 10.0I-lCi/sec o R-27 Current Alarm 3.25 E+3 I-ICi/sec o Plant Vent Sample 1.85 E-5 I-ICi/cc Plant Vent Flow 3.21 E+4 Condenser Air In leakage 5.8 1 of 10 Appendix Job Performance Measure Form ES-C-1 Worksheet Task Standard: . A VC Pressure Relief Gaseous Release Permit 013 Attachment

1) is correctly filled Required Materials:

General

References:

Initiating You are the BOP operator and the CRS has directed you to perform a manual VC Pressure Relief Gaseous Release Permit in accordance with 3-S0P-WDS-013.

Time Critical Task: No Validation Time: 25 Min 2 of 10 Appendix Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 1. Performance Step: Obtain correct procedure Standard:

Obtain current revision of 3-S0P-WDS-013 Review Precautions and Limitations CUE: All pal are satisfactory to continue.

Comment: 2. Performance Step: Review NOTES before Step 4.1.1 Standard:

Reviews Notes Comment: Performance Step: Record VC Pressure Relief as system to be released on Attachment 1

Enters "VC Pressure Relief' on Attachment 1 Comment: Procedure Step 4.1.1 4. Performance Step: Record current date/time on Attachment 1 Standard:

Enters current date/time on Attachment 1 Comment: Procedure Step 4.1.2 3 of 10 Appendix Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark...J)

5. Performance Step: ASSIGN permit number and RECORD on Attachment

1. Standard:

Records Permit Number. Given in Initial Conditions Comment: Procedure Step 4.1.3 6. Performance Step: Record current VC pressure on Attachment 1 Standard:

Records 1.5 psig on Attachment

1. Given in Initial Conditions Comment: Procedure Step 4.1.4 7. Performance Step: VERIFY one of the following conditions satisfied: R-12 operable. R-11 operable AND a VC noble gas sample is obtained.

R-12 is operable.

Given in Initial Conditions Comment: Procedure Step 4.1.5 Performance Step: Determine VC Noble Gas concentration using one of the following methods

• R-12 reading Standard:

Determines R-12 reading is available Comment: Procedure Step 4.1.6 4 of 10 Appendix Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,J) Performance Step: If using R-12, THEN circle "R-12 Monitor" and Enter the following on Attachment 1 R-12 reading for Concentration of Nobel Gas (I-lCi/cc) NA for Sample #, Date, and Time for Grab Sample Circle R-12 Monitor; Enter 7.170 E-7lJCi/cc and enter NA for Sample #, Date and Time Comment: Procedure Step 4.1.8 '" 1 O. Performance Determine calculated release rate ( R ) IJCi/sec and record on Attachment 1

R = (2.83E+OS cc/sec)

• 7.170 E-7lJCi/cc R= 2.02E-1 Comment: Procedure Step 4.1.9 '" 11. Performance Determine available release rate D in I-ICi/sec with R-27 In Service (given in Initial Conditions) 3.2SE+3 IJCi/sec -10 I-ICi/sec

= 3.24E+3 I-ICi/sec Comment: Procedure Step 4.1.10.1 12. Performance Step: Record Discharge Monitor on Attachment 1 Standard:

Record R-27 on Attachment 1 Comment: Procedure Step 4.1.11 5 of 10 Performance Information (Denote critical steps with a check mark ...J) 13. Performance Step: Record Actual Alarm Setpoint on Attachment 1 Standard:

Records 3.25E+3 !-ICi/sec Comment: Procedure Step 4.1.12 14. Performance Step: R is less than D THEN record NA calculated alarm setpoint on Attachment 1 Standard:

Records NA on Attachment 1 Comment: Procedure Step 4.1.13 Performance Step: If calculated release rate R is greater than available release rate D THEN obtain authorization for higher release rate.

Determines R is less than 0 and authorization is not required Comment: Procedure Step 4.1.14 Performance Step: If R-27 is operable THEN enter an alert setpoint at a value below current alarm setpoint at CRS discretion and record on Attachment

1.

Records any value less than 3.25E+3 I-lei/sec Comment: Procedure Step 4.1.15 6 of 10 Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,j) ..J 17. Performance Step: If R-12 is operable THEN determine R-12 calculated auto closure setpoint and record on Attachment 1 Standard:

R-12 Setpoint ::::: 7.0E4

• 3.53E-6 ::::: 2.471 E-1 Comment: Procedure Step 4.1.16.1 18. Performance Step: Standard:

IF necessary THEN adjust R-12 auto closure setpoint to less than or equal to calculated value Determines setpoint adjustment is NOT necessary Comment: Procedure Step 4.1.16.2 19. Performance Step: Standard:

When permit is complete.

THEN record NA for the following:

• Release path valve alignment verification

• Volume

• Activity

• Iodine 131 Activity

• Calculated Alarm Setpoint

• Emax

• E

• RCV-014 setting Records NA on Attachment 1 Comment: Procedure Step 4.1.17 Terminating Cue: JPM Complete 7 of 10 Appendix C Page 8 Form ES-C-1 AlTACHMENT1, GASEOUS PI;RMIT (Pag.1 of 1) , .....'NjI,;,,*;**

.' .....

'. J.1Cifsee

.. J1cvsec\

..:. .

";..."4,'_:.::.:-....

..

Resu..119l;tgr tJ A, ..

ANSWER 8 of 10 Appendix C Page 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Result: SAT or Examiner's signature and date: __________9 of 10

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

1. The Unit is operating at 100% power. 2. All radiation monitors are operable.

3. VC Pressure is 1.5 psig

• Permit Number 120204

• Radiation Monitor Data: o R-12 Current Reading 7.170 E-7 lJCi/cc o R-12 Current Alarm 1.5 E-6 !-ICi/cc o R-14 Current Reading 9.948E-7 !-ICi/cc o R-14 Current Alarm 1.5E-5 !-ICi/cc o R-15 Current Reading 1.32 E-6 !-ICi/cc o R-27 Current Reading 10.0 lJCi/sec o R-27 Current Alarm 3.25 E+3 !-ICi/sec o Plant Vent Sample 1.85 E-5 !-ICi/cc Plant Vent Flow 3.21 E+4 Condenser Air In leakage 5.8 Initiating Cue: You are the BOP operator and the CRS has directed you to perform a VC Pressure Relief Gaseous Release Permit in accordance with 013.

---

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point 3 Task No: 2000070132 Task Title: Review a Quadrant Power Tilt Calculation by Hand 1940012125 KIA

Reference:

SRO -4.2 Job Performance Measure No: SRO Admin 1 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 measure will be Initial

• Plant is at 100% power BOL.

• The Control Room personal computer is unavailable.

• A Reactor Operator performed an Manual Quadrant Power Tilt Ratio Calculation

• The Reactor Operator recommended a 9% power reduction.

Task Standard:

QPTR properly calculated.

Required Materials:

Calculator, GRAPH-NI-2 General

References:

3-S0P-RPC005A, GRAPH-NI-2 Initiating Cue: You are Spare SRO and The SM directed you to REVIEW a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of OOSA. Determine if RO recommendation is accurate.

Time Critical Task: No 1 of 13 Appendix C Job Performance Measure Form ES-C-1 Validation Time: 45 minutes 2 of Appendix Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ",j) 1. Performance Step: Obtain correct procedure Standard:

Obtain current revision of 3-S0P-RCP-005A Comment: 2. Performance Step: Review Note before Step 1 Standard:

Reviews Note Comment: Performance Step: ENSURE appropriate meter range for detectors A and B, for each operable NIS Power Range Channel Ensures range meter indication between 1/3 and 2/3 of full scale Comment: Attachment Step 1.0 3 of 13 Form Performance Information (Denote critical steps with a check mark v) 4. Performance Record the following current information:

Records the following on Attachment 1

• Date T odays Date

• Time Current Time * % Power Indicated Power Attachment Step 2.0 Performance Step: RECORD UPPER and LOWER detector currents on operable NIS Power Range drawers Reviews Table 1 Entries -All Correct Provide the Candidate with detector currents for use in the remainder of the JPM Attachment Step 3.0 6. Performance If power range current amp is unavailable This step is Not Applicable Attachment Step 3.1 4 of 13 Appendix Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) ..J 7. Performance CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps by full power zero axial offset detector current from GRAPH-NI-2 Reviews entered data and calculate corrected detector current ratios 41 Upper 799/790=1.011 41 Lower 823/850=0.968 42 Upper 818/825=0.991 42 Lower 843/822=1.026 43 Upper 875/890=0.983 43 Lower 873/875=0.998 44 Upper 832/830=1.002 44 Lower 896/910=0.985 Identify incorrect values used for 41 and 42 lower detector actual currents (Channel 41 current was entered in Channel 42 location and vice versa) Comment: Attachment Step 4 5 of 13 Performance Information (Denote critical steps with a check mark -V) Performance Step: DETERMINE both upper and lower Average Normalized Ratios CALCULATE average normalized ratios for Upper detectors:

=41U + 42U + 43U + 44U = 1.011+0.991+0.983+1.003 4 = 0.995 CALCULATE average normalized ratios for Lower detectors:

=41L+42L+43L+44L

= 0.968+1.026+0.998+0.985 4 = 0.994 The actual calculated value for the lower average normalized ratio is the same as the correctly calculated value. This is coincidence.

Comment: Attachment Step 5 6 of 13 Appendix Page 7 Performance Information (Denote critical steps with a check mark ..J) "9. Performance DETERMINE both upper and lower Quadrant Power Tilt as follows Standard:

=Highest Ratio of 41 U + 42U + 43U + 44U = 1.011 Average Ratio 0.997 =1.014 =Highest Ratio of 41 L + 42L + 43L + 44L = 1.026 Average Ratio (Step 6.2) 0.994 =1.032 Identifies that based on earlier mistake QPTR is incorrectly calculated.

Actual QPTR is 1.014. Comment: Values obtained by the candidate may vary depending on how decimal places they carry. Attachment Step 6.0 10. Performance Step: Record Highest Quadrant Power Tilt calculated Standard:

Observes 1.032 on attachment 1 is incorrect value Comment: Attachment Step 7.0 7 of 13 Form Performance Information (Denote critical steps with a check mark -I) V 11. Performance Step: If Quadrant Power Tilt exceeds 1.02 in either top or bottom of core ... Standard:

Determines actual QPTR does not exceed 1.02 Determine RO power reduction recommendation is NOT correct. No reduction in power is necessary.

Comment: Attachment Step 8.0 Terminating Cue: JPM Complete 8 of 13 Appendix C Page 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Result: SAT or Examiner's signature and date: __________9 of 13 Appendix C Simulator Setup Form ES-C-1 Set Simulator to any At Power IC. 10 of Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• Plant is at 100% power BOL.

• The Control Room personal computer is unavailable.

• A Reactor Operator performed an Manual Quadrant Power Tilt Ratio Calculation

• The Reactor Operator recommended a 9% power reduction.

Initiating Cue: You are Spare SRO and The 8M directed you to REVIEW a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of 80P-RPC-OOSA.

Determine if RO recommendation is accurate.

_p.ppendix C Initial Conditions Form ES-C-1 Actual Detector Currents Channel Top 41 799 42 818 43 875 44 832 Appendix C Initial Conditions Form ES-C-1 3-GRAPH-NI-2 Rev. NIS FULL POWER DETECTOR CURRENTS Cycle (Values updated based on 17C20 flux map at 99.9% RTP) FACE PLATE Channel TOP N41 790 N42 825 N43 890 N44 830 IR DETECTOR CURRENT LIMITS FOR USE IN 3-POP-1.3 N35 Current limit (Amps) N36 Current limit (Amps) 4%RTP 0.85 E-05 1.72 8%RTP 1.70 E-05 3.44 Written By: Signature Reviewed By: Signature Approved By Signature Effective Date: Today's Date No: 3-S0P-RPC-OOSA Rev: S QUADRANT POWER TILT CALCULATIONS Page 10 of 13 ATTACHMENT MANUAL QUADRANT POWER TILT (Page 1 of NOTE A detector current meter range should be selected which places meter between 1/3 and 2/3 of full ENSURE appropriate meter range is selected for detectors A and B, for each operable NIS Power Range channel. RECORD the following current information:

Date -rOOM{ Time % Power l oll7o RECORD individual upper and lower Power Range detector currents indicated on each operable NIS Power Range drawer in the following Table 1: NOTE Enter "0", if one power range channel is out of service. TABLE 1 I POWER RANGE CHANNEL UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT 41 1'1'1 42 iif 43 t13 44 tttc, No: 3-S0P-RPC-OOSA Rev:S QUADRANT POWER TILT CALCULATIONS Page 11 of 13 ATTACHMENT MANUAL QUADRANT POWER TILT (Page 2 of WARNING Electrical shock hazard inside drawer. !E power range current amp is CONTACT I&C to obtain a DVM current reading for the appropriate drawer. RECORD DVM reading(s) in Table 1 of Step 3.0. CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps recorded in Table 1 of Step 3.0 by full power zero axial offset detector current obtained from last incore/excore calibration (3-Graph-NI-2, NIS Full Power Detector Currents):

Indicated 3-Graph-NI-2 3-Graph-NI-2 Normalized Detector Current Current Ratio Current Current Ratio 41 Upper + Jqo = 41 Lower + fj5Q = D.*Q'8 42 Upper + aZI) = 42 Lower +

J. = II ..:1I. 43 Upper + = 43 Lower + a1{" =

44 Upper

+ = 44 Lower + = D.

i No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS I Page 1 2 of 1 3 ATTACHMENT 1 MANUAL QUADRANT POWER TILT (Page 3 of 5.0 DETERMINE both upper and lower Average Normalized Ratios as follows: NOTE When Reactor Power is less than or equal to 75%, then 3 NIS power ranqe channels can be used. (Reference 5.2.2) If ONLY 3 NIS power range channels are in service, then "0" is entered for the inoperable channel, AND the sum of the currents is divided by 3. 5.1 CALCULATE average normalized ratio for Upper detectors:

41U + 42U + 43U + 44U = 3* or 4* 4-=

• See note above 5.2 CALCULATE average normalized ratio for Lower detectors:

41L + 42L + 43L + 44L == 3* or 4*

• See note above previous sub-step NOTE Upper Quadrant = Highest Normalized Ratio for Upper Detector (Step Power Tilt Average Normalized Ratio for Upper Detector (Step Lower Quadrant = Highest Normalized Ratio for Lower Detector (Step Power Tilt Average Normalized Ratio for Lower Detector (Step 6.0 DETERMINE both upper and lower Quadrant Power Tilt as follows: 6.1 CALCULATE Quadrant Power Tilt for Upper detectors: HighestRatioof41U,42U,43U,or44U

= '.011 = Average Ratio (Step 5.1) 6. c¥i1 6.2 CALCULATE Quadrant Power Tilt for Lower detectors:

Highest Ratio of 41 L, 42L, 43L, or 44L = Average Ratio (Step 5.2)

No: 3-S0P-RPC-OOSA Rev:S QUADRANT POWER TILT CALCULATIONS Page 13 of 13 ATIACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 4 of 4) RECORD highest Quadrant Power Tilt calculated in Steps 6.1 OR 6.2: Highest Quadrant Power Tilt: __

_________ !E Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following: VERIFY requirements of LCO 3.2.4 are met NOTIFY CRS AND SM ENTER calculated Quadrant Power Tilt in the Narrative Log REVIEW Attachment 1 for satisfactory completion:

I Control Room Supervisor Date I Time I Shift Manager Date I Time WHEN complete, THEN FORWARD this Quality Record to the Operations Department Records Custodian.

Date

---* Procedure Use Is: Control Copy: ____

Ii'J Continuous Nuclear Northeast o Reference Effective Date: o Information Page 1 of 15 3-S0P-RPC-OOSA, Revision:

S QUADRANT POWER TILT CALCULATIONS Approved By: I Procedure Sponsor, RPOI Desi nee Date Team 3D Procedure Owner EDITORIAL I No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT L ____________________

..l...--Pa_

g_e_2_0_f_1_3

_____REVISION

SUMMARY

(Page 1 of 2) REASON FOR REVISION Updated to eliminate poor practices and ensure procedure contains proper level of detail.

SUMMARY

OF CHANGES Moved and revised former Step 1.2, of Purpose, to Step 2.2.1 of P&Ls, General Information (Editorial 4.6.13). Moved and revised former Step 1.3, of Purpose, to Step 2.2.2 of P&Ls, General Information (Editorial 4.6.13). Deleted former P&L 2.1 regarding RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors.

Other methods exist to ensure requirements are met (Editorial 4.6.12). Split Section 2, Precautions and Limitations, into 2 parts: 2.1, Precautions and Limitations and 2.2, General Information (Editorial 4.6.10). Added P&L 2.1.1 regarding use of uncorrected detector outputs to be consistent with Unit 2 procedure (Editorial 4.6.11). Added P&L 2.2.3 regarding short term Tilt spikes with alarm actuation fol/owing RCS boron changes to be consistent with Unit 2 procedure (Editorial 4.6.11). Added "IF Reactor Power is less than or equal to 75%, THEN" to Step 3.1 to clarify SR 3.2.4.1 (Editorial 4.6.13). Deleted former Step 3.2 regarding reactor power being greater than 50%. Per Reactor Engineering, QPTR can be performed at lower power, but becomes less accurate (Editorial 4.6.12). Added Step 3.2 "IF Reactor Power is greater than 75%, THEN VERIFY aI/ four NIS channel upper and lower detectors are in service" to clarify SR 3.2.4.1 (Editorial 4.6.11) Added Note prior to Step 4.1 regarding normalization factors not being available fol/owing refueling or detector maintenance (Editorial 4.6.11). Split Section 4.1 into two parts: 4.1, Manual Quadrant Power Tilt Calculation and 4.2, Computer Network Program Quadrant Power Tilt Calculation (Editorial 4.6.14).

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 3 of 13 (Page 2 of 2) Changed Step 4.2.8 from "SELECT" to "ENTER" and deleted bullet regarding clicking "OK" and appropriate option button as there are no 'select' options (Editorial 4.6.13). Added 2 bullets to Note prior to Step 4.2.8 to clarify when 3 or 4 operable NIS Power Range channels are used (EditoriaI4.6.11). Deleted former Step 4.1.13 regarding performing RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors.

Other methods exist to ensure requirements are met (Editorial 4.6.12). Deleted former Steps 4.1.14.2,4.1.14.3 and 4.1.14.4 as these are all included in Tech Spec 3.2.4 (EditoriaI4.6.12). Added bullet to Step 4.2.13 to enter calculated Quadrant Power Tilt in the Narrative Log (Editorial 4.6.11). Added Reference 5.2.2, SR 3.2.4.1 (Editorial 4.6.4). Deleted former Reference 5.3.1, RA-11.1, as it is no longer mentioned in procedure (Editorial 4.6.12). Added Reference 5.6.1, 0-NF-303, Core Quadrant Power Balance as an Interface Document (Editorial 4.6.11). Added Reference

5.7.1 UFSAR

Section 7.6.2 (Editorial 4.6.11). Deleted former Step 4.0 of Attachment 1 regarding performing RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors.

Other methods exist to ensure requirements are met {Editorial 4.6.12). Added "when Reactor Power is less than or equal to 75%, then 3 NIS power range channels can be used" to Note in Step 5 of Attachment 1 to clarify when 3 operable NIS Power Range channels can be used (Editorial 4.6.13). Added bullets to Step 8.0 of Attachment 1 to verify requirements of LCO 3.2.4 are met, notify CRS and SM and to enter QPTR in the Narrative log (Editorial 4.6.11). Changed Step 10.0 of Attachment 1 to forward Attachment 1 to Operations Staff to simplify the action. Placing in Operations Log binder has the same result of forwarding to Operations Staff (Editorial 4.6.13).

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 4 of 13 TABLE OF CONTENTS Section Title Page 1.0 PURPOSE ...............................

., ........................................................................................ 2.0 PRECAUTIONS AND LIMITATIONS

................................................................................. 3.0 PREREQUISITES

.............................................................................................................. 4.0 PROCEDURE

.................................................................................................................... 4.1 Manual Quadrant Power Tilt Calculation

.................................................................... 4.2 Computer Network Program Quadrant Power Tilt Calculation

...................................

5.0 REFERENCES

................................................................................................................ 6.0 RECORDS AND DOCUMENTATION

.............................................................................. Attachments ATIACHMENT 1 MANUAL QUADRANT POWER TILT CALCULATION

................................

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 5 of 13 PURPOSE 1.1 This procedure provides guidance for the preparation of quadrant power tilt calculations in accordance with Technical Specification surveillance requirement SR 3.2.4.1. PRECAUTIONS AND LIMITATIONS Precautions and Limitations Uncorrected detector outputs SHALL NOT be used to calculate quadrant power tilt because they do NOT represent relative core power in their associated quadrant. General Information WHEN in MODE 1 with greater than 50 percent of rated thermal power AND quadrant power tilt exceeds 1.02, THEN VERIFY QPTR is within limit by calculation once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (Reference 5.2.11 WHEN in MODE 1 with greater than 50 percent of rated thermal power AND either one upper OR lower quadrant power tilt alarm monitors are inoperable, THEN verify QPTR is within limit by calculation once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND after load change greater than 10 percent of rated power. (Reference 5.2.31 Short term Quadrant Power Tilt calculation spiking with possible Plant Computer System alarm actuation can occur immediately following Reactor Coolant System (RCS) boron changes. These short term spikes, (approximately five minutes duration), should not be considered significant, as they are transitory in nature. PREREQUISITES IF Reactor Power is less than or equal to 75%, THEN VERIFY a Minimum of three NIS channel upper and lower detectors are in service. (Reference 5.2.2) IF Reactor Power is greater than 75%, THEN VERIFY all four NIS channel upper and lower detectors are in service.

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 6 of 13 4.0 PROCEDURE NOTE Following refueling or detector maintenance, prior to performance of initial at-power incore flux mapping operations.

NIS detector current output normalization factors will not be available.

During this period. NIS detector current outputs must be logged as required below. but quadrant tilt calculations cannot be performed.

4.1 Manual

Quadrant Power Tilt Calculation IF desired to perform a manual calculation, THEN GO TO An ACHMENT 1. MANUAL QUADRANT POWER TILT CALCULATION.

4.2 Computer

Network Program Quadrant Power Tilt Calculation NOTE A detector current meter range should be selected which places meter indication between 1/3 and 2/3 of full scale. VERIFY appropriate meter range is selected for detectors A and B for each operable NIS channel. RECORD the individual upper and lower power range detector currents indicated on each operable NIS Power Range drawer in the following table: TABLE POWER RANGE CHANNEL UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT 41 42 43 44 I No: 3-S0P-RPC-00SA Rev:sl QUADRANT POWER TILT CALCULATIONS 7 of 13 WARNING Electrical shock hazard inside drawer. IF a power range detector current amp reading is unavailable, THEN: CONTACT I&C to obtain a DVM current reading for the appropriate drawer. RECORD DVM reading(s) in the Table provided in Step 4.2.2. ACCESS the QPTR Program (\\ipcfsetsp002\OPERATIONS\OPS General\IP3\Software\Unit 3\QPTR\QPTR.exe). IF the network is unavailable AND CCR computer is operational, THEN: OBTAIN the QPTR Program CD from Shift Manager's office. INSERT CD in a CCR computer AND OPEN QPTR Program. CLICK the "Click Here to Start" button to retrieve 100% NIS currents from 3-Graph-N 1-2. COMPARE the latest NIS currents against the 3-Graph-NI-2 values. IF the 100% NIS currents do not match 3-Graph-NI-2, THEN CLICK the "No" button AND ENTER 100% currents and 3-Graph-NI-2 revision number in the text boxes when prompted. IF the 100% NIS currents match the latest revision of 3-Graph-NI-2, THEN click the "Yes" button. WHEN prompted, THEN ENTER today's date, the current time and the current % power.

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 8 of 13 NOTE This program can be used for either 3 or 4 operable NIS Power Range channels. Three operable NIS Power Range channels can be used when Reactor Power less than or equal to 75%. (Reference All four operable NIS Power Range channels are required when Reactor Power greater than ENTER the correct number of operable NIS Power Range channels. ENTER appropriate NIS information from Table of Step 4.2.2 in the white text boxes. !E a power range channel that is out of service, THEN ENTER "0" for the applicable channel in the white text boxes. CLICK on the CALCULATE QPTR button to show the current QPTR. CLICK on the PRINT RESULTS button to obtain computer printout of the quadrant power tilt calculation. IF Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following:

• VERIFY requirements of LCO 3.2.4 are met.

• NOTIFY CRS AND SM.

• ENTER calculated Quadrant Power Tilt in the Narrative Log. WHEN QPTR calculation program is no longer required, THEN CLICK "Quit Program". OBTAIN CRS and SM signatures for the completed QPTR printout. PLACE completed QPTR computer printout in Operations Log binder.

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 9 of 13 5.0

5.1 Commitment

5.2 Technical LCO 3.2.4 Action SR TRO 3.2.A Action

5.3 Development

5.4 Historical Development 3PT -W022 , Quadrant Power Tilt 5.5 5.6 Interface O-NF-303, Core Quadrant Power 3-Graph-NI-2, NIS Full Power Detector

5.7 UFSAR

Section 6.0 RECORDS AND 6.1 The following required records resulting from this procedure controlled and maintained in accordance with the IP3 Records

• Attachment 1, Manual Quadrant Power Tilt Calculation Sheet

• Computer-generated printout of Quadrant Power Tilt Calculation 6.2 The following documentation is required to be controlled or maintained accordance with the IPEC Records Retention

• None No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS I Page 10 of 13 ATTACHMENT MANUAL QUADRANT POWER TILT (Page 1 of NOTE A detector current meter range should be selected which places meter indication between 1/3 and 2/3 offull scale. ENSURE appropriate meter range is selected for detectors A and B, for each operable NIS Power Range channel. RECORD the following current information:

Date_____ Time,_______ % Power______ RECORD individual upper and lower Power Range detector currents indicated on each operable NIS Power Range drawer in the following Table 1: NOTE Enter "0", if one power range channel is out of service. POWER RANGE CHANNEL 41 42 43 44 TABLE 1 UPPER DETECTOR CURRENT LOWER DETECTOR CUR No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT Page 11 of ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 2 of 4) WARNING Electrical shock hazard inside drawer. IF power range current amp is CONTACT I&C to obtain a DVM current reading for the appropriate drawer. RECORD DVM reading(s) in Table 1 of Step 3.0. CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps recorded in Table 1 of Step 3.0 by full power zero axial offset detector current obtained from last incore/excore calibration (3-Graph-NI-2, NIS Full Power Detector Currents):

Indicated 3-Graph-NI-2 3-Graph-NI-2 Normalized Detector Current Current Ratio Current Current Ratio 41 Upper + = 41 Lower + 42 Upper + = 42 Lower + 43 Upper + = 43 Lower 'T' 44 Upper 'T' = 44 Lower +

No: 3-S0P-RPC-005A Rev:sl QUADRANT POWER TILT CALCULATIONS , Page 12 13 An ACHMENT MANUAL QUADRANT POWER TILT (Page 3 of DETERMINE both upper and lower Average Normalized Ratios as follows: NOTE When Reactor Power is less than or equal to 75%, then 3 NIS power range channels can be used. (Reference 5.2.2) If ONLY 3 NIS power range channels are in service, then "0" is entered for the inoperable channel, AND the sum of the currents is divided by 3. CALCULATE average normalized ratio for Upper 41U + 42U + 43U + = = 3* or 4*

• See note above CALCULATE average normalized ratio for Lower 41L + 42L + 43L + == 3* or 4*

• See note above previous sub-step NOTE Upper Quadrant = Highest Normalized Ratio for Upper Detector (Step Power Tilt Average Normalized Ratio for Upper Detector (Step Lower Quadrant = Highest Normalized Ratio for Lower Detector (Step Power Tilt Average Normalized Ratio for Lower Detector (Step DETERMINE both upper and lower Quadrant Power Tilt as follows: CALCULATE Quadrant Power Tilt for Upper

= Highest Ratio of 41U, 42U, 43U, or44U = __= Average Ratio (Step 5.1) CALCULATE Quadrant Power Tilt for Lower Highest Ratio of 41 L, 42L, 43L, or 44L = __= = Average Ratio (Step 5.2)

No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT Page 13 of ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 4 of 4) RECORD highest Quadrant Power Tilt calculated in Steps 6.1 OR 6.2: Highest Quadrant Power Tilt____________

_ !E Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following: VERIFY requirements of LCO 3.2.4 are met NOTIFY CRS AND SM ENTER calculated Quadrant Power Tilt in the Narrative Log REVIEW Attachment 1 for satisfactory completion:

I Control Room Supervisor Date I Time I Shift Manager Date I Time WHEN complete, THEN FORWARD this Quality Record to the Operations Department Records Custodian.

Date

---

Appendix Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Task No: 2000100132 Task Title: Review Deborating Demineralizer In-Service Time Calculation 2.1.25 Job Performance Measure KIA

Reference:

SRO -4.2 No: SROAdmin2 NRC Examiner:

Facility Date: Method of testing: Simulated Actual Performance x Classroom x

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: A Deborating Demineralizer In-Service Time Calculation was prepared by the Spare RO CVCS is aligned for normal operation RCS filter is in service The demineralizer has been final rinsed Reactor Power is 100% Control Bank D is at 228 steps Current Tavg is 568°F Desired Tavg 569°F ITC -33.4 pcmrF Letdown Flow is 84 gpm Current Boron Concentration is 98 ppm Deborating Bed 31 is in service Deborating Demineralizer effluent is 14 ppm Sampled 0100 today. The SM had determined that the Deborating Demin will be used to reduce RCS boron concentration.

Task Standard:

In-Service Time properly calculated.

10f6 Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials:

Calculator Procedure General

References:

3-S0P-CVCS-004 Initiating Cue: You are a spare SRO and the SM has directed you to review the Deborating Demineralizer In-Service Time using 3-S0P-CVCS-004 step 4.3.4. Time Critical Task: No Validation Time: 45 min 20f6

_A-Jp'-'p_e_n_di_x_c

_________.........::...P..::::a""g-=-e..::::3

_________

Performance Information (Denote critical steps with a check mark ;/) 1. Performance Step: Calculate the change in T avg on Attachment 1 Standard:

Ll T avg =TF -TI L'1 Tavg =569°F -568°F Tavg =1°F Calculation is correct Comment: Procedure Step 4.3.4.3 Performance Step: Calculate the change in RCS Boron Concentration for the change in Tavg on Attachment 1 Standard:

L'1 B =Ll Tavg

• ITC

• IBW L'1 B =1°F * -33.4 pcmrF*-O.1074 ppmlpcm B = 22.1 ppm Calculation is correct Comment: Procedure Step 4.3.4.4 Performance Step: Calculate Boron Efficiency for selected deborating demineralizer Standard:

BE =1 -(BO/BI) BE =1 -(14/98) BE =.86 Clculation is correct Comment: Procedure Step 4.3.1.1 30f6 Performance Information (Denote critical steps with a check mark ...J) -v 6. Performance Step: Calculate G -gallons of water using Graph CVCS-3 Standard:

From Nomograph

-20,000galions This is NOT the correct value Comment: Procedure Step 4.3.4.5. This value can be obtained if candidate uses 30 ppm for boron concentration change -v 7. Performance Calculate the Deborating Demineralizer in-service time T =G / (LF

• BE) T =20,00gallons

/ (84 gallons/min

• 0.86) T =276.8 minutes This is NOT the correct value due to incorrect G from previous step. Comment: Procedure Step 4.3.4.5 Terminating Cue: "IPM Complete 4 of6 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Result: SAT or Examiner's signature and date:

___________50f6 Appendix C Initial Conditions Form ES-C-1 Initial Conditions: A Deborating Demineralizer In-Service Time Calculation was prepared by the Spare RO CVCS is aligned for normal operation RCS filter is in service The demineralizer has been final rinsed Reactor Power is 100% Control Bank D is at 228 steps Current Tavg is 568°F Desired Tavg 569°F ITC -33.4 pcmrF Letdown Flow is 84 gpm Current Boron Concentration is 98 ppm Deborating Bed 31 is in service Deborating Demineralizer effluent is 14 ppm Sampled 0100 today. The SM had determined that the Deborating Demin will be used to reduce RCS boron concentration.

Initiating Cue: You are a spare SRO and the SM has directed you to review the Deborating Demineralizer In-Service Time using 3-S0P-CVCS-004 step 4.3.4.

PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 19 of 37 CAUTION When more than one unsaturated demineralizer is placed in service at the same then the margin to cold shutdown boron must be evaluated by

4.3.4 Determining

Deborating Demineralizer In-Service Time IF RCS has been borated to cold shutdown +100 ppm boron concentration AND the Reactor Trip Breakers are OPEN, THEN GO TO Step 4.3.5 to place Deborating Demineralizer(s}

in service as required (aSSist in crud burst cleanup). IF RCS Boron Concentration is less that 3 PPM AND Reactor Power is less than 99%, THEN GO TO Step 4.3.5 to place Deborating Demineralizer in service as required.

NOTE This method is intended for use at approximately 100% power due to the basis Attachment 2, Inverse Boron Worth vs Boron CALCULATE the change in Tavg required on Attachment 1 as follows: 6 Tavg = TF -TI. where 6 T avg = Required change in T avg (OF) TF= Final Tavg(OF) TI = Initial Tavg(OF)

PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 20 of 37 CALCULATE the change in RCS Boron concentration for the change in Tavg on Attachment 1 as follows: dB =d Tavg It ITC

• IBW, where Ll B = Change in RCS Boron Concentration (ppm) d Tavg =Required change in Tavg (OF) ITC =At Power Isothermal Temperature Coefficient for the initial Tavg{pcmJoF), from Graph RV-5B IBW =Inverse Boron Worth (ppmJpcm) for the initial ReS Boron concentration, from Attachment 2, Inverse Boron Worth VS Boron Concentration CALCULATE the Deborating Demineralizer in-service time on Attachment 1 as follows: T =G I (LF

• BE), where T = required Deborating Demineralizer in-service time (Min) G =Amount of dilution water required for the change in boron concentration (gals),from Graph CVCS-3, (Dilution Nomograph for Hot ReS 580°F) or CCR computer.

LF = Letdown Flow (gpm), from FI-134 BE = Boron Efficiency for the selected Deborating Demineralizer PLACE completed Attachment 1, Deborating Demineralizer In-service Time Calculations, in Daily Log Binder for Operations Staff to review and file.

PLACING THE CVCS DEMINERALIZERS No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 36 of 37 ATTACHMENT 1 DEBORATING DEMINERALIZER IN-SERVICE TIME CALCULATIONS (Page 1 of 1) 4.3.4.3 Required change in Tavg: 4.3.4.4 Change in RCS Boron concentration:

=__,___.. _"._3.....

__11 -0.'/)1t./ 6 B (ppm) 6 T avg (OF) ITe (pcm/OF) IBW (ppm/pcm) 4.3.1.1 Boron Efficiency for Deborating Demineralizer:

3 l OIOQ 'TODAy Bed No. Sample Time Sample Date _.8"--(,,,=--_

= 1 -(14 I ) BE BO (ppm) BI (ppm) 4.3.4.5 Deborating Demineralizer in-service time: = DOO I ( c.f 11 0

• S , ) G (gal) LF (gpm) BE I

• _JV: 25 No: 3-S0P-CVCS-004 PLACING THE CVCS IN OR OUT OF SERVICE Page: 37 of ATTACHMENT 2 INVERSE BORON WORTH VS BORON CONCENTRATION (Page 1 of 1) "().105 I I I I I I I I I I I I I I 1 I I I I I I I I I I I I I 1 I I I I "'Il'. l. __ .LLLI. ..1 _ I J _I.. I . I _I. I __LJ..I_L 1.l L.J ...l I I I I I I I I I

• I I

• I I

• I

• I *

• I I II" III I I I I I 1 L.LL. J.L NOTE: This graph for use at Hot Full Power I I I I I I AI Rods Out conditiona onIyl I , I I I 1 I *I .1_ l * .1.1.*1 .1.. _1.1*..l_L.. --t-I_I* ..1.-_L.. ..... ..J_t_ ., **&.. L I. .I.I.L.II . I 1 I I IIII I1II III III1 I I 1 I I I I I I I I I IIII II1I IIII IIII I 1 I I I I I I I I.LL I .I .L L . I. J,., _1_ . .I.LI. .I l.1 I. I

• _I I .1 I:::!: I I I I I I I 1 I I I I I I I I -1" "1-\ I I I I I I I I U I I I I I I I I I I I I 1 I I I I I I I I I I I I I* I "().106I I 1 I I I , I I , I

• I I t I I I I I I I I I I , I I I I I 1 1 a.. 1 I I I 1 I . 1 J. I J. I I . 1-.1. I. 1 a.. I I I I 1 I I I I I I I I 1 I I I I I I I I I -I I I I 1 1 I I I I I 1 1.c:. t I I I I . I L I 1. I .. I

• 1..1 l. I I I. I I I 0 I I I I I 1 I 1 I I I I I 1 I 1 I

• 1 I I I *I I 1 I 1I I I I I I I I 1 I I I I I I I I I __I.I .1 .I L *I_ I I 1 1 I 1 I .I .1.*1 I. I. II .1 J c:: I I I I 1 I I I I

• I I 1 1 I I I I I I 1 0 I I I I , I I I I I I 1 I 1 I J I I I I I I I .... I I .I I I. I .I I I. J . *1. 1 I . .1. J. 1..1*. I l.. I .1. 1 .1 .. I 0 I I I I

• I I I I I I I , I I I I I I I 1 I I I I en I I I I , I 1 II I I I 1 I I I 1 I I I I I I I I -0.107 I I I t 1 I I , I I I I I I I I I I I

• I I I Q.) I I I I I I I I I I I I I I I I 1 I I I I I I 1 > I 1.1. I I 1 . I . I I I. I I. f 1.1 I. . I.. I I I I I. 1 L I I I I I I I 1 I I I I I 1 I 1 I 1 I I I I 1 I I I..5 I I I I I I I I 1 I I I I I I I I I I I I I I I I I 1 I I..LI .1 .1 I I 1 1 _I I I I I I I I I I 1 I I I I I I II I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I 1 I I I I I I I I I I 1.1 I I I I I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I I I , I I I I I I I I 1 I I 1 I I I 1 I I I I I I I 1 I I I 1 I I I I I I I I , 1 I I I I I 1 I I I I I I 1 I I I I . I I I I I 1.1 I I I I I I I I I I ,.I II I I I I 1 I I I t 1 I I I I I 1 I I I I I I I I I I I I I I I I I I I I I I I I I I 1 t I I I I I f I I I I I I -L-l..().10a 90 100 0 10 20 30 40 50 60 70 80 Boron Concentration (PPM)

Unit 3 Rev. 0

• DILUTION NOMOGRAPHFOR t'tOT ReS 580 0 ". Reviewed By' K _ . 10,000 20,000 50,000 100,000 DILUTION WATER GAL. PPM BORON 1M COOLANT PPM BORON DILUTION . Approved By cvcs-3 paqe 3 of J Section

---

Appendix Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point 3 Task No: 2000390131 Task Title: Review a Tagout 1940012213 Job .....""'.,.,.....,n"I Measure KIA

Reference:

SRO -4.3 No: SROAdmin 3 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 performance measure will be Initial The unit is in Cold Shutdown with no fuel in the reactor The eSOMS Clearance Module is unavailable. The Shift Manager has determined that 33 Charging Pump must be tagged out for seal replacement. Clearance Number is 3C20 Tagout Number is CH-038. No deficiencies exist on valves identified in tagout boundary An RO prepared a manual tagout for 33 Charging Pump Task Standard:

Manual Tagout Reviewed and errors located Required Materials:

None General

References:

EN-OP-102, Protective and Caution Tagging 3-COL-CVCS-001 Chemical and Volume Control System EN-OP-102-1, Protective and Caution Tagging Forms & Checklists 9321-F-27363 Flow Diagram Chemical and volume Control System Sheet 1 1 of 11 Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: You are a spare 8RO and the 8M has directed you to review a manual tagout for 33 Charging Pump using EN-OP-102 and EN-OP-102-01.

Time Critical Task: No Validation Time: 45 minutes 2 of 11 Initial Conditions Performance Information (Denote critical steps with a check mark >/) 1. Performance Step: Standard:

Comment: 2. Performance Step: Standard:

Obtain Correct Procedure Obtains EN-OP-102 and EN-OP-102-01 Ensure requirement of Attachments 9.1 and 9.2 of OP-102 are followed Review Attachment 9.1 and 9.2 Comment: Procedure Step 5.3 [1] 3. Performance Step: Review Scope of Work Standard:

Tagout Required for emergent work. Given in Initial Conditions Comment: Procedure Step 5.3 [2] Performance Step: Determine Safe Work Boundary for 33 Charging Pump Seal Replacement Review Plant Prints 9321-F-27363 Comment: Procedure Step 5.3 [2] (g)

Appendix Initial Conditions Form ES-C-1 Performance Information (Denote critical steps with a check mark "'./) Performance Step: Boundary Valves should be reviewed outstanding deficiencies Standard:

No deficiencies exist on valves identified in tagout boundary -Given in Initial Conditions CUE: No deficiencies exist on valves identified in tagout boundary Comment: Procedure Step 5.3 [3] -:r6.Performance Step: Standard:

Comment: Utilizing the Isolation Boundaries, Review the tagout and identify the following errors: Valve CH-409 Charging Pump Recirc Valve was NOT included on Tagout Valve CH-284 Charging Pump Inlet Isolation Restoration Configuration is CLOSED CH-1175D Charging Pumps Suction Line Drain Placement Configuration should be OPEN CH*1175D Charging Pumps Suction Line Drain Restoration Configuration should be CLOSED See Attached Answer Key Initial Conditions Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) Key Elements From Attachment

9.2 Tagging

Sequence All Tagouts require tags to be hung and cleared in the order specified on the Tag Hang sheet or Tags To Be Removed sheet. When no definitive order is required for certain components of a T agout, the Operations Supervisor may specify a given order number for multiple components (e.g., multiple components listed on the Tagout may be given order number "5" when their sequence relative to each other is not important). Recommended tagging order for pumps A. Control switch B. Breaker for main power C. Breakers for auxiliary power (motor heater, oil pumps, etc.) D. Discharge valve E. Suction valve F. Other components within scope of Tagout Terminating Cue: JPM Complete

---

ATTACHMENT 9.3 T AGOUT TAGS SHEET CLEARANCE:

3C20 MANUAL,____ T AGOUT: SI-038 1 2 I 3 4 5 6 7 8 9 10 11 Tag Type Danger Danger Danger Danger Danger Dange r Danger Danger Danger Danger Danger ,,-----,

Equipment Equipment 33 Charging Pump Control Switch rCR 33 Charging Pump Breaker Control Fuses 480V Room Bus 5A 33 Charging Pump Breaker 1480V Room Bus 5A 33 Charging Pump Outlet solation Charaina Pump Cell 33 Charging Pump Outlet solation to Seal Injection 33 Charaina Pump Cell 33 Charging Pump Recirculation Isolation 33 Charging Pump Cell CH-281 33 Charging Pump Relief and Recirculation Line Outlet Isolation 33 Charging Pump Cell CH-284 33 Charging Pump Inlet solation 33 Charaina Pump Cell CH_418 33 Charging Pump Suction Stabilizer Drain 33 Charaina Pump Cell 33 Charging Pump Suction ine Drain 33 Charaina Pump Cell 33 Charging Pump Suction Stabilizer Vent Cap Cell 1 2 3 4 5 6 7 8 9 10 11 Pull to Racked Out Closed Closed -" ,,---, Closed Closed ---" "-,, Closed Open --------Open Cap Removed ,,-,,--" Place, Place. Rest. 1st Rest. 2nd Placement!

1st Verif 2nd Verif Rest. Restoration Verif Verif Removal

---

...-RClteJIiI"l'lE:

COQfiguration DatefTime Tao Notes CRITICAL Auto I I I ,,-,,"-Installed/On

,,--Racked In ,,--"',\-'---" Open " Open "-,, .... ,---" CRITICAL Open Open ,,----, "" -" "----,, "----,, CRITICAL Open Closed "---"',.--" ,,---, ------'" ,--" "-,, CRITICAL Closed Cap Installed . ",L__" ...,,_' ---------L".

ATTACHMENT

9.3 TAGOUT

TAGS SHEET CLEARANCE:

3C20 MANUAL,____ T AGOUT: -----PH419 33 Charging Pump Stabilizer 12 Danger 12 Open b3 Charging Pump 33 Charging Pump Outlet 13 Danger 13 Cap Removed Cap b3 Charaina Pump

.. -

33 Charging Pump Outlet Vent 14 Danger 14 Open (33 Charging Pump -----1----....._... -

VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Result: SAT or UNSA Examiner's signature and date: __________

Appendix C Initial Conditions Form ES-C-1 Initial Conditions: The unit is in Cold Shutdown with no fuel in the reactor The eSOMS Clearance Module is unavailable. The Shift Manager has determined that 33 Charging Pump must tagged out for seal Clearance Number is 3C20 Tagout Number is CH-038. No deficiencies exist on valves identified in tagout boundary An RO prepared a manual tagout for 33 Charging Pump Initiating Cue: You are a spare SRO and the SM has directed you to review a manual tagout for 33 Charging Pump using EN-OP-102 and EN-OP-102-01.

---

ATTACHMENT

9.3 TAGOUT

TAGS SHEET TAGOUT: _______CLEARANCE:

3C20 MANUAL CH-038 ......Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement!

Serial Type Equipment Description Place. Placement 1 st Verif 2nd Verif Rest. Restoration Verif Verif Removal No. Equioment Location SeQ. Configuration DatefTime DatefTime ConfiQuration DatefTime DatefTime Tag Notes Charging Pump Pullout 1 Danger Switch 1 Or Auto Pull to Lock k:;CR --.----......* ...Charging Pump 2 Danger Breaker Control Fuses 2 Removed/Off Installed/On 480V Room Bus 5A 33 Charging 3 Danger Breaker 3 Racked Out Racked In 1480V Room Bus 5A f.-H-236 33 Charging Pump Outlet solation 4 Danger 4 Closed Open 133 Charaino Pump ",H-238 33 Charging Pump solation to Seal 5 Danger 5 Closed Open 133 Charaino Pump Cell 33 Charging Pump Relief and Line Outlet Isolation 6 Danger 6 Closed Open 133 Charging Pump Cell --.---.... f---..----------

33 Charging Pump Inlet Isolation I 7 Danger 7 Closed Closed 133 Charaino Pump Cell ---------......----------...... _._-",H-418 33 Charging Pump Stabilizer 8 Danger 8 Open Closed 33 Chargina Pump l;H-1175D 33 Charging Pump ine 9 Danger 9 Closed Open 33 Charging Pump CH-419 33 Charging Pump Stabilizer Vent 10 Danger 10 Cap Removed Cap Installed 133 Charaina Pump Cell f.-H-419 33 Charging Pump Suction Stabilizer Vent 11 Danger 11 Open Closed 133 Chanling Pump Cell ...-------..._L.__'-----.........---

---

---

ATTACHMENT

9.3 TAGOUT

TAGS SHEET TAGOUT: _______CLEARANCE:

3C20 MANUAL CH-038 ""H::103 33 Charging Pump Outlet Vent 12 Danger 12 Cap Removed Cap Installed Charging Pump Cell 33 Charging Pump Outlet Vent 13 Danger 13 Open Closed 33 Charging Pump Cell

---

No:3-COL-CVCS-001 Rev: 27 AND VOLUME CONTROL SYSTEM Page 27 of 41 Des. Oper Actual Pos. Pos. Initial IV 2.12 Charging Pumgs 55' Elev. -PAS 2.12.1 Charging Pumps Local Control Station 31 Charging Pump Control Switch Remote 32 Charging Pump Control Switch Remote 33 Charging Pump Control Switch Remote CH-AOV-200A 45 GPM Letdown Orifice Control Switch Auto AR CH-AOV-200B 75 GPM Letdown Orifice Control Switch Auto AR CH-AOV-200C 75 GPM Letdown Orifice Control Switch Auto AR a PI-142 Vent (next to charging pumps stabilizer heater panel) Shut 2.12.2 31 Charging Pump Cell CH-1175B 31 Charging Pump Suction Line Drain Shut CH-278 31 Charging Pump Inlet Isolation Open CH-273 31 Charging Pump Relief and Recirculation Line Outlet Isolation LO CH-230 31 Charging Pump Outlet Isolation CH-232 31 Charging Pump Outlet to Seal Injection NED-275 31 Charging Pump Seal Overflow Isolation CH-407 31 Charging Pump Recirculation Isolation Shut CH-1 31 Charging Pump Strainer DIP Hi Side Isolation Shut Capped __CH-2 31 Charging Pump Strainer DIP Low Side Isolation Shut Capped

CHEMICAL AND VOLUME 2.12 (CONTINUED)

CH-102 32 Charging Pump Outlet Vent CH-415 32 Charging Pump Suction Stabilizer Drain CH-416 32 Charging Pump Suction Stabilizer Vent CH-417 32 Charging Pump Suction Stabilizer Drain Line Vent 32 Charging Pump Transfer Switch 2.12.4 33 Charging Pump Cell CH-113 Charging Pumps Discharge Header Vent CH-1175D 33 Charging Pump Suction Line Drain CH-284 33 Charging Pump Inlet Isolation CH-281 33 Charging Pump Relief and Recirculation Line Outlet Isolation CH-236 33 Charging Pump Outlet Isolation CH-238 33 Charging Pump Outlet Isolation to Seal Injection NED-280 33 Charging Pump Seal Tank Overflow Isolation CH-409 33 Charging Pump Recirculation Isolation CH-5 33 Charging Pump Strainer DIP Hi Side Isolation CH-6 33 Charging Pump Strainer DIP Low Side Isolation CH-103 33 Charging Pump Outlet Vent No:3-COL-CVCS-001 Rev: 27 Page 29 of 41 Des. Oper Pos. Actual Pos. Initial IV Shut Capped Shut Shut Capped Shut Capped Normal Locked Shut Capped Shut Open LO Open Open Open Shut Shut Capped Shut Capped Shut Capped

! No:3-COL-CVCS-001 Rev: 27[ CHEMICAL AND VOLUME CONTROL SYSTEM

• Page 30 of 41____________________Des. Oper Pos. Actual Pos. Initial IV 2.12 (CONTINUED)

CH-418 CH-419 CH-420 CH-199 33 Charging Pump Suction Stabilizer Drain 33 Charging Pump Suction Stabilizer Vent 33 Charging Pump Suction Stabilizer Drain Line Vent Emergency Boration Line Drain (in overhead)

Shut Shut Capped ____ Shut Capped Shut Capped 2.12.5 Charging Pump Cells Passage Way CH-229 o PT-142 &PI-142 Root Isolation PT-142 &PI-142 Isolation Open Open 2.13 Boric Acid Transfer Pumps 55' Elev. -PAB 2.13.1 31 Boric Acid Transfer Pump CH-376 CH-363 CH-367A CH-364 CH-360 Boric Acid Batch Tank Outlet Isolation 31 Boric Acid Transfer Pump Primary Water Supply Isolation 31 Boric Acid Transfer Pump Batching Tank Supply Isolation 31 Boric Acid Transfer Pump Suction Isolation 31 Boric Acid Transfer Pump Discharge Isolation to 31 Boric Acid Filter Shut Shut Shut Open AR CH-361 CH-355A 31 Boric Acid Transfer Pump Discharge Isolation to 31 Boric Acid Storage Tank PI*190A Isolation AR Open ATTACHMENT 9.3 T AGOUT TAGS SHEET TAGOUT: ____________

__CLEARANCE:

MANUAL,_____ Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement!

Serial Type Equipment Description Place. Placement 1st Verit 2nd Verif Rest. Restoration Verif Verif Removal No. 1 Danger I I 2 Danger ! 3 I Danger I I! I I Danger Is I I I Danger 6 I Danger I 8 Danger Danger I Danger 11 Danger I Equipment Location 33 Charging Pump ,-,ontrol Switch CCR 33 Charging Pump Breaker Control Fuses Bus 5A 33 Charging Pump Breaker 480V Room Bus 5A CH*236 33 Charging Pump Outlet solation 33 Charging Pump Cell l.H*238 33 Charging Pump Outlet solation to Seal Injection 33 Charging Pump Cell l.H-409 33 Charging Pump Recirculation Isolation 33 Charging Pump Cell ,-,H*281 33 Charging Pump Relief and Recirculation Line Outlet Isolation 33 Cell CH*284 33 Charging Pump Inlet solation 33 Charging Pump Cell CH-418 33 Charging Pump Suction Stabilizer Drain 33 Charging Pump Cell CH-1175D 33 Charging Pump Suction ine Drain 33 Charging Pump Cell CH-419 33 Charging Pump Suction Stabilizer Vent Cap 33 Charging Cell Seq. Configuration Datefrime Datefrime Seq Configuration Datefrime Datefrime Tag Notes ! I1 Or CRITICAL Pull to I +-.1 2 Removed/Off Installed/On I 3 Racked Out CRITICAL Racked In I 4 Closed CRITICAL Open -, 5 Closed CRITICAL Open 6 Closed CRITICAL Open i " 7 Closed Open 8 Closed CRITICAL Open 9 Open Closed 10 Open Closed 11 Cap Removed CRITICAL Cap Installed 1

! 12 Danger 13 Danger *... 14 Danger ATTACHMENT 9.3 CH-419 33 Charging Pump Suction Stabilizer Vent 33 Charging Pump Cell CH-103 33 Charging Pump Outlet Vent Cap 33 Charging Pump Cell CH-103 33 Charging Pump Outlet Vent 33 Charging Pump Cell 12 13 -14 Open Cap Removed -Open CRITICAL ...TAGOUT TAGS SHEET Closed Cap Installed Closed ....

m 0 i '"w ii; ,,':;' ".

"J! .... 'f,;

..

J.J'. ; 1i Ii "/ r-=

!:fl 9:UO; p e § '< t 'i. :r

---

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point 3 Task No: 2000180132 Task Title: Review a VC Pressure Relief Release Permit 1940012311 Job Performance Measure KIA

Reference:

SRO -4.3 No: SROAdmin4 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 performance measure will be Initial

1. The Unit is operating at 100% power. 2. All radiation monitors are operable except R-27 3. VC Pressure is 1.5 psig

• Permit Number 120204

• Radiation Monitor Data: o R-12 Current Reading 7.170 E-7 j..ICi/cc o R-12 Current Alarm 1.5 E-6 j..ICi/cc o R-14 Current Reading 9.948E-7 j..ICi/cc o R-14 Current Alarm 1.5E-5 j..ICi/cc o R-15 Current Reading 1.32 E-6 j..ICi/cc o R-27 Current Reading OOS o R-27 Current Alarm OOS o Plant Vent Sample 1.85 E-5 j..ICi/cc Plant Vent Flow 3.21 E+4 Condenser Air In leakage 5.8 1 of 12 Appendix Job Performance Measure Form ES-C-1 Worksheet Task Standard: . A VC Pressure Relief Gaseous Release Permit 013 Attachment

1) is correctly filled Required Materials:

General

References:

Initiating You are the FSS and the SM has directed you to review a manual VC Pressure Relief Gaseous Release Permit in accordance with SOP-WDS-013.

Time Critical Task: No Validation Time: 25 Min 2 of 12

__________

.___________Form ES-C-1 Performance Information (Denote critical steps with a check mark --J) 1. Performance Step: Obtain correct procedure Standard:

Obtain current revision of 3-S0P-WDS-013 Review Precautions and Limitations CUE: All P&L are satisfactory to continue.

Comment: 2. Performance Step: Review NOTES before Step 4.1.1 Standard:

Reviews Notes Comment: Performance Step: Record VC Pressure Relief as system to be released on Attachment 1

Checks "VC Pressure Relief' entered on Attachment 1 Correct Comment: Procedure Step 4.1.1 4. Performance Step: Record current date/time on Attachment 1 Standard:

Checks current date/time on Attachment 1 Correct Comment: Procedure Step 4.1.2 3 of 12 Performance Information (Denote critical steps with a check mark "'-1) 5. Performance ASSIGN permit number and RECORD on Attachment

1.

Checks Permit Number entered on Attachment

1. Given in Initial Conditions Correct Comment: Procedure Step 4.1.3 6. Performance Record current VC pressure on Attachment 1

Checks 1.5 psig on Attachment

1. Given in Initial Conditions Correct Comment: Procedure Step 4.1.4 7. Performance Step: VERIFY one of the following conditions satisfied: R-12 operable. R-11 operable AND a VC noble gas sample is obtained.

R-12 is operable.

Given in Initial Conditions Comment: Procedure Step 4.1.5 Performance Step: Determine VC Noble Gas concentration using one of the following methods

• R-12 reading (J.l.Ci/cc)

Determines R-12 reading is available Comment: Procedure Step 4.1.6 4 of 12 Appendix Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,f) '" 9. Performance If using R-12, THEN circle "R-12 Monitor" and Enter the following on Attachment 1 R-12 reading for Concentration of Nobel Gas NA for Sample #, Date, and Time for Grab Sample Checks "R-12 Monitor" Circled Correct Observes incorrect data entered for Concentration of Noble Gas 9.948E-7 entered CRITICAL Should have entered 7.170 E-7 jJCilcc Observes "NA" for Sample #, Date and Time NOT CRITICAL Comment: Procedure Step 4.1.8 '" 10. Performance Determine calculated release rate ( R) jJCi/sec and record on Attachment 1

Observes Calculation performed correctly using incorrect numbers R = (2.83E+05 cc/sec)

• 9.948E-7 fJCi/cc R= 2.81 E-1 CRITICAL Correct Calculation should be 2.02E-1 Comment: Procedure Step 4.1.9 5 of 12 Appendix Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark 11. Performance Determine available release rate 0 in !-lCi/sec with R-27 OOS and R-14 In Service (given in Initial Conditions)

Checks calculation correct (1.5E-5 -9.948E-7)

• 3.21 E+4

• 472 = 2.12E+2 !-lCi/sec Comment: Procedure Step 4.1.10.2 '\J 12. Performance Step: Record Discharge Monitor on Attachment 1 Standard:

Checks R-14 on Attachment 1 Observes R-27 entered on Attachment 1 INCORRECT Comment: Procedure Step 4.1.11 13. Performance Step: Record Actual Alarm Setpoint on Attachment 1 Standard:

Checks 1.5E-5 !-lCi/sec Correct Comment: Procedure Step 4.1.12 Performance Step: If R is less than D THEN record NA for calculated alarm setpoint on Attachment 1

Checks NA on Attachment 1 Correct Comment: Procedure Step 4.1.13 6 of 12 Appendix Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ."J) 15. Performance Step: If calculated release rate R is greater than available release rate D THEN obtain authorization for higher release rate. Standard:

Determines R is less than D and authorization is not required Comment: Procedure Step 4.1.14 Performance Step: If R-27 is operable THEN enter an alert setpoint at a value below current alarm setpoint at CRS discretion and record on Attachment

1.

R-27 is not operable (Given in Initial Conditions)

Comment: Procedure Step 4.1.15 17. Performance If R-12 is operable THEN determine R-12 calculated auto closure setpoint and record on Attachment 1

Checks R-12 Setpoint = 7.0E4

• 3.53E-6 =2.471E-1 Correct Comment: Procedure Step 4.1.16.1 18. Performance Step: IF necessary THEN adjust R-12 auto closure setpoint to less than or equal to calculated value Standard:

Checks setpoint adjustment is NOT necessary Comment: Procedure Step 4.1.16.2 7 of 12 Appendix C Page 8 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) 19. Performance Step: Standard:

When permit is complete, THEN record NA for the following:

• Release path valve alignment verification

• Volume

• Activity

• Iodine 131 Activity

• Calculated Alarm Setpoint

• Emax

• E

• RCV-014 setting Checks NA on Attachment 1 Comment: Procedure Step 4.1.17 Terminating Cue:

Complete 8 of 12 Appendix Page 9 Form ES-C-1 GASEOUS WASTE 3-S0P-Woo-013 Reyo 28 L--____ ...___ _____-'-__

..______.=J AlT ACHMENT GASEOUS WASTE RELEASE PERMIT (Page 1 of Current _ , Tank! Vi,.: I'/l",......,t-System (1) ik I,,'f \(/(j ,')tfa DatelTime (2) te Concentration of Volume (4) /J /!. fe Initial Pressure (5) \. "l psig Noble Gas Grab Sample:(7)

Sample # ,,J Time tJ k. Activity

_____!lCi Noble Gas Iodine 131 Activity (8a) N A.

,___::r,N'e.-+

",.1"", VC Purge Only it \),,)1A.ot Calculated Release Rate (R)(9 :),!:II t--I ",Ci/sec Available Release Rate (D)(10)J.I*'c t.1.",Ci/sec Actual Alarm Selpoln! (12)1.) E" -t.::)

Calculated alarm setpoin! (13) ...J b. !lei/sec Alert selpolnt (14) t-J jlCi/sec R-12 Auto Closure/Alarm Setpoints:

Calculated (15) ;).Ll 1 C -\ llCi/cc Actual (16) 1.5 E -(, llCi/cc !E discharge monitor is OOS, THEN COMPLETE the following: Monitor (17) N A.. _._ placed out service @ __

_ __--"""-'--'--

__ Date Time Vent Sample:(1 5) Sample # W p". Date,_-"yt...:.:."'--

__Time ,J A. Results (1g) !J Is (Noble Gas) Vent flow rate (20) tJ '" cfm Continuous Release Rate (CR)(21),_-"t.J:..;":....:...

___

Release Calculations verified by

___________________Release Path Valve Alignment Verified (23)_______________________Discharge AuthOrized

_ .:-:-____ Release Start

__eRS/SM Final Pressure (26) ____,__psig Release Stop (27),___--____Date Calculations Results: S (28) ______

____________" RCV"014 Setting (31),______% Comments (32) __ANSWER 9 of 12 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Result: SAT or Examiner's signature and date: __________10 of 12 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

1. The Unit is operating at 100% power. 2. All radiation monitors are operable except R-27 3. VC Pressure is 1.5 psig

• Permit Number 120204

• Radiation Monitor Data: o R-12 Current Reading 7.170 E-7 o R-12 Current Alarm 1.5 E-6 o R-14 Current Reading 9.948E-7 o R-14 Current Alarm 1.5E-5 o R-15 Current Reading 1.32 E-6 o R-27 Current Reading OOS o R-27 Current Alarm OOS o Plant Vent Sample 1.85 E-5 Plant Vent Flow 3.21 E+4 Condenser Air In leakage 5.8 Initiating Cue: You are the FSS and the SM has directed you to review a manual VC Pressure Relief Gaseous Release Permit in accordance with 3-S0P-WDS-013.

__ l Appendix I nitial Conditions Form ES-C-1 -S0-P--W--O"-S---O-13---R-ev-:-2-a-l

"" GASEOUS WASTE RE_L_E_A_S_E_S

__..L-__" _______""" Page 37 of 56 ATTACHMENT GASEOUS WASTE RELEASE PERMIT (Page 1 of 1) Current _Tankl \.Ie p((,r..,..,.t' Date/Time (2) \&'d(?o[J C!),V'f evil Permit No" (3) FlO;) () 'f System (1) '" I,,*' ate Time Concentration of Volume (4) fJ A. ft3 Initial Pressure (5) I* s-psig Noble Gas (C)(6) q.ti..Jf;f-7 Grab Sample:(7)

Sample 1'..1 t..

__ Time tJA.. Activity

______

Noble Gas Iodine 131 Activity (8a) tJ A. )J.Ci/cc VC Purge Only Calculated Release Rate (R)(9) ).l!I £--I IlCi/sec Available Release Rate Discharge Monitor (11)_--'-"2:..-

....J'>-1-'--____ Actual Alarm Setpoint (12) !. 5 E" -i.=) pCI/sec Calculated alarm setpoint

___

Alert setpoint (14) __---:..r-J-=--f\

___

R-12 Auto Closure/Alarm Setpoints:

Calculated

__

Actual (16) 1.5£ -l.,

1.E discharge monitor is OOS. THEN COMPLETE the following: Monitor (17) !-..l A. placed out service @ Date Vent Sample:(18)

Sample # t.J " .:-;A.'--__Time tJ A.. Results (19) tJ "-(Noble Gas) Vent flow rate (20) tJ A. cfm Continuous Release Rate (CR)(21

___Release Calculations verified by

___________________Release Path Valve Alignment Verified \4'"'1_____________________Discharge Authorized (24),__-=-=-::::-:-:-

_____ Release Start CRS/8M Date Final Pressure (26) psig Release Stop Date Calculations Results: S (28) ______ Emax fe/min E(30),______ ft 3!min RCV-014 % open I 3-S0P-WDS-013 Rev: GASEOUS WASTE RELEASES 37 of 56 ATTACHMENT GASEOUS WASTE RELEASE PERMIT (Page 1 of 1) Current Date/Time (2)

CU.V'ft"ill\

Permit No. (3) I (}OJoll ate Time Concentration of Volume (4) tJ /1. fe Initial Pressure (5) , * '5 psig Noble Gas (C)(6) q. q&.(t)£-7 /lCilcc Grab Sample:(7)

Sample # tJ A...

__ Time ,J A.

Activity (A}(8)._-'-t..l_A

______,/lci Noble Gas Iodine 131 Activity (8a) N A. /lCi/cc VC Purge Only Calculated Release Rate (R)(9) ::>. I G-I }.lCi/sec Available Release Rate (D)(10)J.t*lc t.J..}.lCi/sec Discharge Monitor (11 )_........"i2=--

.....J>-J-l.--____ Actual Alarm Setpoint (12) Vi t;; -t:)

Calculated alarm setpoint (13) __N_'_b.___

Alert setpoint (14 ) ___r-..l_"'___/lCi/SeC R-12 Auto Closure/Alarm Setpoints:

Calculated (15) :; .Ll16 -\ /lCi/cc Actual (16) 1.5'£ -(,

IF discharge monitor is OOS. THEN COMPLETE the following: Monitor (17) t-J , placed out service @ Date Vent Sample:(18)

Sample # U f:... Date__

__Time tV Results (19) , tJ As-(Noble Gas) Vent flow rate (20) tJ A.. cfm Continuous Release Rate (CR)(21 )_.....;...:tJ:...!\.....;..

____

Release Calculations verified by

__________________Release Path Valve Alignment Verified (23) _____________________Discharge Authorized (24) __==-:-::-_____ Release Start CRS/SM Date Final Pressure (26) _______psig Release Stop Date Calculations Results: S (28) _____Emax (29) _______ft 3/min E(30)______fe/min RCV-014 Setting (31 )______% open Comments:(32)

________________________________

_

. No: 3-S0P-WDS-013 Rev: 28 GASEOUS WASTE RELEASES Page 37 of 56 ATTACHMENT GASEOUS WASTE RELEASE PERMIT (Page 1 of 1) Current _Tank! \Ie System (1) f<< I,,' .f DatelTime (2) te Volume (4) ff Initial Pressure (5) ,. psig Grab Sample:(7)

Sample #

tJ l. Date A.. Activity

____-Jf.lCi Noble Gas Iodine 131 Activity (8a) N A. f.l Ci/ee __-_:rW'Dme-f.

VC POI . c:ku.fo Wi' ny urge Calculated Release Rate (R)(9) c:: -I Ci/sec Available Release Rate (D){10)J.l l c t.l.J,.I.Cilsec

).lCi/sec Discharge Monitor (11) @ Wt'b!4 M.Dni.4trf Actual Alarm Setpoint (12) 1.5" £" -S" Calculated alarm setpoint (13) ,J b. !-lCi/sec Alert setpoint (14) ...., f\ !-lCi/sec R*12 Auto Closure/Alarm Setpoints:

Calculated (15) 1 E. -\ ).lCilee Actual (16) (. c; -(, ).lCi/cc IF discharge monitor is OOS, THEN COMPLETE the following: Monitor (17) ....J l.. placed out service@_--:.N;:...o.;;I'l

>.."--_____..:.::Io.J:....:...;A.:......-Date Vent Sample:(18)

Sample # t.J f1... Date tJ " Time A Results (19) tJ I\c. ).lCi/cc (Noble Gas) Vent flow rate (20) tJ cfm Continuous Release Rate (CR)(21

___

Release Calculations verified by

_________________Release Path Valve Alignment Verified (23),____________________Discharge Authorized (24),__==-=-=-____ Release Start (25),_----,,..---_

CRS/SM Date Final Pressure (26),______psig Release Stop (27),___Date Calculations Results: S (28),____Emax (29),_______fefmin E(30),______fe/min RCV-014 Setting (31),______% Comments: (32),______________________________

---

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point 3 Task No: 1500010532 Task Title: Classify Emergency Events requiring Emergency Plan Implementation 1940012438 Job Performance Measure KIA

Reference:

SRO-4.4 No: Admin-5 Examinee:

NRC Examiner:

Facility Evaluator:

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

1 of 8 Appendix Job Performance Measure Form ES-C-1 Initial Conditions:

A reactor trip occurred approximately 18 minutes ago after 108 days @ 100% reactor power. The trip was automatic due to a loss of 31 Instrument Bus while N41 was OOS for repair. 33 EDG is tagged out for air-start motor replacement following a failed surveillance.

A loss of offsite power occurred during the auxiliary power transfer.

32 EDG has failed to start. The Control Room Supervisor has completed the immediate actions of ECA-O.O and the following conditions exist according to the brief: 31 EDG is operating.

2AT3A tie breaker will not close due to a tripped 3A normal supply breaker with its amber light illuminated. The Con Ed DO has reported a grid stability problem due to severe weather to our South and power should be restored to the region within the hour 33332L and 33332M are OOS and the Buchanan Ring Bus is de-energized 31 Instrument Bus has been reenergized on MCC-34 The Conv NPO and the FSS are working to start the 32 EDG The WF NPO is trying to start the Appendix R EDG 32 ABFP is feeding all SGs adequately RCS pressure is 2050 psig and increasing I&C is investigating the cause of the 3A Bus problem Natural Circulation flow has been verified in the RCS METEOROLOGICAL CONDITIONS:

Wind Speed: 2.8 Wind Direction:

110 degrees @ 10 Stability Class: Task Standard:

Event properly classified and Part 1 form correctly completed within the required time. Required Materials:

General I P-EP-120, Emergency Classification IP-EP-210, Central control Room IP-EP-410, Protective Action Recommendation EAL Wall Chart EAL Technical Basis Document 2 of 8 Appendix C Job Performance Measure Form ES-C-1 Initiating Cue: The Shift Manager has become ill. You are the CRS and you must perform the duties of the Emergency Director until a replacement SM can arrive on site. This is a Time Critical Job Performance You must Classify the event and Complete the NYS Part 1 Inform the examiner when you have classified the Inform the examiner when you have completed the Part 1 Time Critical Task: Yes Validation Time: 25 30f8

_A--'-"'-'ppc....;e;...:..n'-.:::dc:c..ix'--C"--

_________....::...PClge Form ES-C-1 Performance Information (Denote critical steps with a check mark ") 1. Performance Obtain Correct Procedure Obtains IP-EP-120 CUE: Candidate will be given all necessary procedure before the JPM is started. Record the time the is started: _________ "2. Performance Evaluate Plant Status to determine if GE, SAE, Alert, or NUE applies. Determine the highest classification and make declaration.

Standard:

Determines Event is SAE per EAL TIME CRITICAL -Must complete this step within 15 minutes of start of Comment: Record the Time Declaration Made: ________"3. Performance Complete and approve "New York State Radiological Emergency Data Form", IP-EP-115 EP-1 Completes all necessary information on the form and signs the form TIME CRITICAL -Must complete this step within 15 minutes of Time of Declaration (JPM step 2)

Record the Time Form is complete:

_________ 4 of 8

_Appendix Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark 4. Performance Step: Refer to procedure IP-EP-210, Attachment

9.1. Standard

Refers to Attachment

9.1 Comment

Performance Step: Initiate County, State and NRC Notification per IP-EP-115, Form EP-6.

Request a communicator Comment: CUE: Acknowledge the communicator is prepared to make notifications Terminating Cue: JPM Complete 5 of 8 New York Indian Point Energy RADIOLOGICAL EMERGENCY DATA FORM* PART t Notification

1. This is the Indian Point Energy Center with a Part 1 Notification Reactor Status: This ACTUAL EMERGENCY at UNIT 2 3 BOTH Unit ,.... _1"'" (Date) T'tJd.2\.( (Time) hr clock) Shutdown operational

........,..(Date) _-1......._..",'l--___ (Time) i -Ie moults (24 hr clock) The Emergency A Unusual Event B. Alert C. Site Area Emergenc Classilication is: D. General Emergency E, Emergency This Emergency Classification declared ..""'I,-----:",-:at I =-==t (Data) (rima 24 hrr--+----:..........

..---.--.-.-

..3. 4. Release BELOW Federal limits To Atmosphere To Water To Atmosphere To Water D, Unmoni\ored release requiMng evaluation

5. Meiers/Sec at elevation 10 meters 7. 8. B EVACUATE and IMPLEMENT the KI PLAN for the following Sectors C, SHEL TER'IN,PLACE and .IMPLEMENT the KIPLAN for the following Sectors All remaining Areas MONITOR the EMERGENCY ALERT SYSTEM 2 miles around 5*miies downwind 5 miles around 10-miles downwind Entire EE'Z In the following Sectors; 1 2 3

(24 hr clock) -,. I 4ro-V'l11l".t\

The Emergency A. Unusual Event B. Alert C C. Site Area tn-Irs I-¥--2. Classification is: O. General Emergency E. Emergency This Emergency Classification declared

___-=_.at t (Date) (Time 24 hr clock) EAL#: (..1....,

b.{ Q((

101).'" AC

> IS' C)f\cl pDWt'lf" C'lJfe

..,,-th'I>\

1'5 MI "u-ks Release of Radioactive Materials due to the Classified Event: :::8. No Release:>

B. Release BELOW Federal limits To Atmosphere To Water Release ABOVE Federal limits To Atmosphere To Water D. Un monitored release requiring evaluation

5. Wind Meters/Sec at elevation 10 meters 6. Wind Direction: (From) ___IL.,;\!...l)=--

_____ Degrees at elevation 10 meters 7. Stability Class: A B C G) E F G The fnl/owino Protective Actions are ! to be . as soon as A. NO NEED for PROTECTIVE ACTIONS outside the site boundau B. EVACUATE and IMPLEMENT the KI PLAN for the following Sectors C. SHEL TER-IN-PLACE and IMPLEMENT the KI PLAN for the following Sectors All remaining Areas MONITOR the EMERGENCY ALERT SYSTEM 2 milM around 5-miles downwind 5 miles around 1O-miles downwind Entire EPZ In the following Sectors: 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 NOTE: OFFSITE AUTHORITIES SHOULD CONSIDER SHELTER-IN-PLACE of. TAKE KIIF EVACUATION IS NOT FEASIBLE Reported by -Communicator:

_N I.a-=..;W\t'-"""______________

Telephone

__________(Communicators Name) 10. Emergency Director Approval:

________________

Datemme: ___________

_ (Director's Name) Page 1 of Form EP-1, Rev 3 Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point 3 Task No: 0000420501 Task Title: Align Low-Head 51 Flow Path for Hot Leg Recirculation 000011A111 Job Performance Measure A KIA

Reference:

RO-4.2 SRO-4.2 No: Examinee:

NRC Facility Evaluator: Method of Simulated Performance Actual Performance Classroom Simulator X 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:

• It is 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after a large break LOCA with loss of offsite power.

• The SI System is aligned for Cold Leg Recirculation per ES-1.3

• Transfer to hot leg recirculation is desired. Task Standard:

The SI System in aligned for Hot Leg Recirculation with 32 and 33 HHSI Pumps Operating.

Required Materials:

General

References:

1. -ES-1.4 Transfer to Hot Leg Recirculation Initiating Cue: You are the ATC and the CRS has directed you to transfer to Hot Leg Recirculation in accordance with ES-1.4 steps 1 through 11. Time Critical Task: No Validation Time: 20 1 of 13 Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 1. Performance

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

Comment: Procedure Step 1 4. Performance Step: Standard:

Comment: Obtain correct procedure Obtain current revision of 3-ES-1.4 Review Caution and Note before Step 1 Reviews Caution and Note CHECK Low-Head Recirc flow Observe flow on FI-946A through 0 on Panel SBF-2 Review Note before Step 2 Reviews Note 2 of 13 Performance Information (Denote critical steps with a check mark >/) ..J 5. Performance Step: Standard:

Align Non-BIT Hot Leg Injection Valves:

• Close 856J and 856H

• Open 856B Rotate switches for 856 J and H to CLOSE Rotate switch for 856B to OPEN All above switches are on Panel SBF-2 Comment: Procedure Step The sequence of operation of the above valves is important ..J 6. Performance Step: Standard:

Align Non-BIT Hot Leg Injection Valves:

• Close 856E and 856C

• Open 856G Rotate switches for 856 E and C to CLOSE Rotate switch for 856G to OPEN All above switches are on Panel SBF-2 Comment: Procedure Step 3 The sequence of operation of the above valves is important.

7. Performance Step: Check HHSI Hot Leg Injection valve status Standard:

Verify 8568 or 856G OPEN Comment: Procedure Step 4 3 of 13 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) 8. Performance Step: Dispatch Nuclear NPO to deenergize the following valves

• 856G

• 856E

• 856C

• 856J

• 856H

• 856B Standard:

Contact NPO using radio and direct deenergizing valves CLlE: Acknowledge as Nuclear NPO to Deenergize valves Comment: Procedure Step 5 NOTE: Booth Operator Deenergize valves listed above 9. Performance Step: Check Recirc Pumps only one running Standard:

Observes only both Recirc Pumps Operating.

Places one Recirc Pump in Trip Pull Out Comment: Procedure Step 6.a 4 of 13 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) 10. Performance Step: Standard:

Dispatch NPO to verify the following valves CLOSED

• IV-1403

• IV-1447

• IV-1448

• IV-1464

• IV-1465

• IV-1479 Contact NPO using radio and direct verifying valves CLOSED CUE: Acknowledge as Nuclear NPO. Report "All Valves are Closed". Comment: Procedure Step 6.b.1 11. Performance Step: Standard:

Dispatch NPO to verify the following valves OPENED

• SI-MOV-850A

• ISI-MOV-850C Contact NPO using radio and direct verifying valves OPENED Comment: Procedure Step 6.b.2 CUE: Acknowledge as Nuclear NPO 5 of 13 Appendix Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ."J) 12. Performance Step: Standard:

Ensure the following valves are OPEN

• 888A

• 888B

• 1869A

• 1869B

• 1835A

• 1835B

• 1852A

• 1852B Verify valves listed above are opened All of the valves listed above are located on Panel SBF-1 Comment: Procedure Step 6.c 13. Performance Step: Ensure the following valves are OPEN

• 888A

• 888B Rotate switches for above valves to OPEN position Both of the valves listed above are located on Panel SBF-1 Comment: Procedure Step S.c 6 of 13 Appendix Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y) 14. Performance Step: Ensure the following valves are OPEN

• 1869A

• 1869B

• 1835A

• 1835B

• 1852A

• 1852B Verify valves listed above are opened Rotate switch for 1869A to Open All of the valves listed above are located on Panel SBF-1 Comment: Procedure Step 6.c 15. Performance Place SI Pump Suction Low Pressure Alarm Block switch to UNBLOCK Rotate Switch to UNBLOCK on Panel SBF-1 Comment: Procedure Step 6.d 16. Performance Low Pressure Alarm on Observes alarm not illuminated Comment: Procedure Step 6.e 7 of 13 Appendix Page 8 Form ES-C-1 Performance Information (Denote critical steps with a check mark -,J) ..J 17. Performance Step: Place Safety Injection Recirc Switch 6 to OFF position Standard:

Rotate switch to OFF Comment: Procedure Step 6.f 18. Performance Start High Head Safety Injection Pump 31 Observes that 31 HHSI Pump does not start, then places switch in TRIP PULLOUT Go to Step 8 Comment: Procedure Step 7.a " 19. Performance Step: Start High Head Safety Injection Pump 33 Standard:

Rotate switch for 33 HHSI pump to Start Comment: Procedure Step 8.a 20. Performance Step: Check BIT header loop injection flow Standard:

Verify stable flow on Loop 2 Comment: Procedure Step 8.b 21. Performance Step: Check HHSI pump status Standard:

Observes 33 HHSI pump running Comment: Procedure Step 9 8 of 13 Appendix C Page 9 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V) 22. Performance Step: Check status of 31 and 33 HHSI pumps Standard:

Verify only 33 HHSI pump is running Comment: Procedure Step 9.b 23. Performance Step: Check HHSI pump 32 status Standard:

Verify 32 HHSI pump SHUTDOWN Comment: Procedure Step RNO 9.b.1 9 of 13 Appendix Page 10 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/) 29. Performance Check control switches for non-running HHSI pumps in Trip Pullout Standard:

Verifies 31 HHSI pump switch in Trip Pullout Comment: Procedure Step 9.d 30. Performance Step: high-head injection flows established in at least 1 header Standard:

Observes flow in both loops on FI-925 and FI-982 Comment: Procedure Step 9.e '\J 31. Performance Step: Terminate Low Head Recirculation Standard:

Rotate switches for the following to CLOSE

• 746 (Not Critical already closed)

• 747

• 899A

• 899B The switches above are located on Panel SGF Comment: Procedure Step 10 Terminating Cue: JPM Complete 10 of 13 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:

Result: SAT or Examiner's signature and date: __________11 of 13 Appendix C Simulator Setup Form ES-C-1 12 of Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• It is 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after a large break LOCA with loss of offsite power.

• The SI System is aligned for Cold Leg Recirculation per ES-1.3

• Transfer to hot leg recirculation is desired Initiating Cue: You are the ATC and the CRS has directed you to transfer to Hot Leg Recirculation in accordance with ES-1.4 steps 1 through 11.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point 3 Task No: 0100180431 Task Title: Respond to a Pressurizer Low Pressure Alarm 000027A101 Job Performance Measure Sim B KIA

Reference:

RO -4.0 SRO-3.9 No: Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance x Classroom Simulator x 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 plant is operating at 100% power

• No Equipment is Out of Service Task Standard:

Pressurizer pressure stable, reactor tripped with 33 and 34 RCPs tripped. Required Materials:

None General

References:

3-ARP-003 Initiating Cue: You are the ATe Time Critical Task: No Validation Time: 1 of 7 Appendix Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) NOTE: Candidate may diagnose failed open Spray Valve at any time during this JPM. The exact order of actions before the Reactor Trip is not important, and they may be performed in any order. The reactor must be tripped before the Reactor Coolant Pumps are tripped. 1. Performance Step: Acknowledge Pressurizer Low Pressure Alarm and refer to ARP Standard:

Observe alarm and retrieve ARP from holder Comment: Candidate may recognize pressure lowering before alarm annunciates.

2. Performance Step: Verify alarm by observing PRZR Pressure Standard:

Observe pressure decreasing on all 4 channels Comment: ARP Step 3.1 3. Performance Determine if Channel or Controller Failure has occurred Determine NOT instrument failure (All 4 channel indications decreasing)

Determine NOT a controller failure (Controller output calling for heaters. Pressurizer heaters will eventually energize).

Comment: ARP Step 3.2 20f7 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark 4, Performance Comment: ARP Step 5, Performance Comment: ARP Step 6, Performance Comment: ARP Step 7, Performance Comment: ARP Step IF the Pressurizer heaters or sprays are NOT operating properly, THEN PLACE Pressurizer Pressure Master Controller in MANUAL and ATTEMPT to establish RCS pressure at 2235 psig, Transfer controller to Manual (T-bar up) and output adjusted to Heaters (Left of nUll) If Pressure is low, then check:

• PORVs Closed

• PRZR Spray and Aux Spray Closed

• PRZR Heaters Energized Identifies Pressurizer Pressure is low and one Spray Valve is Open If PRZR PORV are NOT closed THEN close PORVs Observes PORVs are closed and no action is required If Spray Valve(s) are not closed Close Spray Valve in Manual Transfer controller to Manual (T-bar up) and output adjusted to Close (Left) 30f7 Appendix Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J> 8. Performance Step: IF PRZR Spray Valve does NOT close, THEN CLOSE PRZR Spray Valve by removing power fuse from back of Foxboro controller for affected PRZR Spray Valve. Standard:

Observes Spray Valve NOT Closed and removes controller from Flight Panel. When controller is removed, then fuse is removed from back. Comment: ARP Step 3.4.3.2 '\J 9. Performance If Spray Valve(s) can NOT be closed, Then TRIP the Reactor Identifies spray valve will not close; depresses the Rx TRIP button on Panel FCF Comment: ARP Step 3.4.3.3.a

'\J 10. Performance Trip 33 and 34 Reactor Coolant Pumps Verifies Reactor Tripped then rotates RCP switches to STOP position Comment: ARP Step 3.4.3.3.b

11. Performance Step: Go To E-O Reactor Trip or Safety Injection Standard:

Observes conditions to verify reactor tripped Comment: ARP Step 3.4.3.3.c Terminating Cue: JPM Complete 40f7 Appendix C Page 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Result: SAT or UNSA Examiner's signature and date: __________50f7 Appendix C Simulator Setup Form ES-C-1 Reset Simulator to any 100% Ie Need Malfunctions to prevent Spray Valve from Closing 6of7 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The plant is operating at 100% power

• No Equipment is Out of Service Initiating Cue: You are the ATC

---Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point 3 Task No: 003*010*04*01 Task Title: RCP #1 Seal Failure Actions KIA

Reference:

003000A2.01 Job Performance Measure No: Sim-C RO -3.5 SRO -3.9 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance x Classroom Simulator X Plant------'----READ TO THE I will explain the initial conditions, which steps to simulate or discuss, and provide cues. When you complete the task successfully, the objective for this job measure will be Initial Conditions:

Plant is at indicated power level. A malfunction is in progress on RCP. The CRS has directed you to perform the actions of AOP-RCP-1.

Reactor Pump Task Standard:

AOP-RCP-1 actions Required Materials:

General Initiating Cue: You are the ATC and the CRS has directed you to perform the actions of AOP-RCP-1.

Reactor Coolant Malfunction for the indicated malfunction on 34 RCP. Time Critical Task: No Validation Time: 10 minutes SIM-D rev. 0 1 of 7 Appendix C 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark) 1. Performance Step: Determine if reactor trip is required:

• Checks motor winding temp> 250°F with Tave > 540°F

• Checks upper or lower motor bearing temp> 200°F

• Checks shaft vibration>

20 mils

• Checks shaft vibration>

15 mils and increasing

• Checks Frame vibration>

5 mils

• Checks Frame vibration>

3 mils and increasing

• Checks seal delta-p < 200 psid

• Checks seal inlet temp> 225°F

• Checks seal outlet temp> 235°F Standard:

Determines reactor trip required goes to step 4.2 Comment: Procedure Step 4.1 2. Performance Step: Are Reactor Trip Breakers Closed Standard:

Observes red lights illuminated

-Reactor Trip Breakers are closed Comment: Procedure Step 4.2 " 3. Performance Step: Trip the reactor Standard:

Reactor manually tripped CUE: CRS directs the rest of the crew to perform E-O immediate actions. You are to continue with the subsequent actions of AOP-RCP-1.

Comment: Procedure Step 4.3 "4. Performance Step: Stop 34 Reactor Coolant Pump Standard:

Places 34 RCP Control Switch to stop. Comment: Procedure Step 4.4 SIM-D rev. 0 2 of 7 Performance Information (Denote critical steps with a check mark) 5. Performance Step: Initiate E-O, Reactor Trip or Safety Injection Standard:

E-O initiated CUE: CRS directs the rest of the crew to perform E-O immediate actions. You are to continue with the subsequent actions of AOP-RCP-1.

Comment: Procedure Step 4.5 6. Performance Step: IAA T RCP #1 seal inlet temperature is > 225°F the dispatch NPO to close CH-241 D 34 RCP Seal Injection Flow Control Valve Standard:

Observes #1 seal inlet temperatures greater than 225 0 dispatches NPO to close valve. and CUE: Acknowledge as NPO and report valve is closed Comment: Procedure Step 4.6 "7. Performance If 33 or 34 RCP shutdown then close affected spray valve -Closes PC-455G Places controller PC-455G to manual and reduces output to 0 (closed).

Comment: Procedure Step 4.7 8. Performance Step Was RCP Shutdown due to #1 seal return flow> 6 gpm Standard:

Determines RCP NOT secured due to High Seal Return Flow Comment: Procedure Step 4.8 SIM-D rev. 30f7 Form ES-C-1 Performance Information (Denote critical steps with a check mark) Performance Step Was RCP Shutdown due to #1 seal return flow < 0.84 gpm and Seal Temperatures Increasing?

Determines RCP was secured due to Low flow and Increasing Seal Inlet temperature Comment: Procedure Step 4.10 '" 10. Performance IAAT 34 RCP has stopped rotating then manually close the seal return valve 2610 Observes flow stable at 20 -30% on loop 34. 2610 closed by placing control switch on panel SAF to close. Comment: Procedure Step 4.23 11. Performance Are EOPs in Use Standard:

Determines EOP are in use Goes to step 4.29 Comments:

Procedure Step 4.24 and 4.25 Performance Step: When directed by the SM Return to procedure and step in effect. Standard:

Comments:

Terminating Cue: JPM is Complete SIM-D rev. 4 of 7 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 UNSA T Examiner's signature and date: ___________

_ SIM-D rev. a 5 of 7 Simulator Setup Reset simulator to IC-11 The malfunctions below will simulate a failure closed of 34 RCP #1 Seal resulting in heating up of the water surrounding the pump bearing and out of the #1 Seal. Insert Malfunction:

• MAL-RCS013D Final Value 20% Ramp 10 Seconds (#2 seal failure)

• ANN-SAF-1-1 OFF (Reactor Coolant Pump Standpipe High Level)

• IND-RCS024D OFF #34 RCP Standpipe Level Off Normal Indicator Light

• IND-CVC015 Final Value 235 Ramp 180 Seconds (Seal Inlet Temp Increasing)

• IND-CVC016 Final Value 252 Ramp 180 Seconds (Seal Outlet Temp Increasing)

Reset Simulator to IC-155 SIM-D rev. 0 6 of?

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

Plant is at indicated power level. A malfunction is in progress on 34 RCP. The CRS has directed you to perform the actions of AOP-RCP-1, Reactor Coolant Pump Malfunction.

Initiating Cue: You are the ATC and the CRS has directed you to perform the actions of AOP-RCP-1, Reactor Coolant Malfunction for the indicated malfunction on 34 RCP. SIM-D rev. 0 7 of 7 Appendix Job Performance Measure Form ES-C-1 Worksheet Indian Point Task No: 0590060301 Facility:

Place Main Feed Reg Valve Controllers in Automatic Task Title: 059000A403 Job Performance Measure No: Sim D KIA

Reference:

RO-2.9 SRO-2.9 NRC Examiner:

Facility Date: Method of testing: Actual Performance x Simulated Performance Simulator x Plant Classroom 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 plant is at 25% power 32 Main Boiler Feed Pump is in service 31 Main Boiler Feed Pump is in Standby SG Levels are being controlled using the Low Flow Bypass Valves Pre Job Discussion for this evolution has been completed Venting of Steam Flow Transmitters is NOT occurring All required Precautions and Limitations and Prerequisites of 001 are satisfied Task Standard:

31 Main Feed Reg Valve in Automatic control. Required Materials:

General

References:

3-S0P-FW-001 Initiating Cue: You are the ATC and the CRS has directed you to transfer to the Main Feed Regulating Valves, starting with 31 SG, in accordance with 3-S0P-FW-001, Main Feedwater System Operation, section 4.10.2. 1 of 8 Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 15 Minutes 2 of 8 Performance Information (Denote critical steps with a check mark ,j) 1. Performance Step: Obtain correct procedure Standard:

Obtains current revision of 3-S0P-FW-001 Comment: 2. Performance Step: Observe CAUTION and NOTE before step 4.10.2 Standard:

Reviews Caution and Note Comment: 3. Performance Step: Verify venting of steam flow transmitters is NOT occurring.

Standard:

Given in Initial Conditions Comment: Procedure Step 4.10.2.1 Performance Step: Verify SG Level is slightly higher than 45% with steam flow and feed flow signals approximately equal Identify 31 SG level slightly higher than 45% and increase feed flow to 32, 33, and 34 SG by opening Low Flow Bypass Valve (Panel FBF) Comment: Procedure Step 4.10.2.2 3 of 8 Appendix Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J) Performance Step: Prepare MFRV for service by unseating the applicable MFRV using Manual Control Rotate large potentiometer on FCV 417 counterclockwise until an increase in feed flow is observed the rotate clockwise to close the valves. (Panel FBF) Comment: Procedure Step 4.10.2.3 '\J 6. Performance Step: Place 31 MFRV in AUTO Standard:

Move controller toggle switch on FCV 417 controllers to left postion Comment: Procedure Step 4.10.2.4 " 7. Performance Adjustthe associated Low Flow Bypass Valve to lower feed flow to slightly less than steam flow Rotate large potentiometer on FCV 417L clockwise (Panel FBF) Comment: Procedure Step 4.1 0.2.5.a 4 of 8 Appendix Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J) '" 8. Performance Step: When associated MFRV starts to OPEN then adjust the Low Flow Bypass Valve as needed to minimize overshoot Standard:

Rotate large potentiometer on FCV 417L counterclockwise when associated MFRV starts to open, (Panel FBF) Comment: Procedure Step 4.10.2.S.b

'" 9. Performance Continue to adjust associated Low Flow Bypass Valve until it is fully closed Continue to Rotate large potentiometer on FCV 417L clockwise in small increments, (Panel FBF) Comment: Procedure Step 4.10.2.S.c

'" 10. Performance Repeat JPM Steps 6-9 as desired Repeat steps to place MFRVs in Auto for as many MFRVs as examiner desires Comment: Terminating Cue: JPM Complete 5 of 8 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Result: SAT or Examiner's signature and date: __________6 of 8 Form ES-C-1 Appendix C Simulator Setup Reset Simulator to Ensure 31 and 32 SG levels are greater than Ensure 33 and 34 SG levels are less than Reset Simulator to 7 of 8 Appendix Initial Conditions Form ES-C-1 Initial Conditions: The plant is at 25% power 32 Main Boiler Feed Pump is in service 31 Main Boiler Feed Pump is in Standby SG Levels are being controlled using the Low Flow Bypass Valves Pre Job Discussion for this evolution has been completed Venting of Steam Flow Transmitters is NOT occurring All required Precautions and Limitations and Prerequisites of 001 are satisfied Initiating Cue: You are the ATC and the CRS has directed you to transfer to the Main Feed Regulating Valves, starting with 31 SG, in accordance with 3...s0P-FW-001, Main Feedwater System Operation, section 4.10.2.

---

_........ __

Appendix C Job Performance Measure Form ES-C-1 Facility:

Indian Point 3 Task No:

Task Title: Start a Fan Cooler KIA

Reference:

RO -3.6 SRO -3.6 Job Performance Measure No: SIM Examinee:

NRC Facility Evaluator: Method of testing: Simulated Performance Actual Performance x Classroom Simulator x 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 measure will be Initial

• The plant is at indicated power

• 31 -34 Containment Fan Cooler Units (FCU) are in operation

• Breaker Maintenance is scheduled for 32 Feu

• Containment Temperature is 87.5°

• Service Water is properly aligned to all FCUs

• All Precautions and Limitations have been satisfied

• 35 FCU was secured 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago for breaker maintenance

• Motor Starting Frequency requirement have been verified.

Task Standard:

35 Fan Cooler Unit is Required Materials: General

References:

3-S0P-C8-010, Containment Recirculation Fan Cooler Operations.

1 of 9 Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: You are the BOP and the CRS has directed you to start 35 Fan Cooler Unit in accordance with 3-S0P-CB-01 O. Time Critical Task: None Validation Time: 10 Minutes 20f9 Form Performance Information (Denote critical steps with a check mark "> 1. Performance

2. Performance

3. Performance Standard:

Obtain correct procedure Obtain 3-S0P-CB-010 Review NOTES before step 4.2.1 Review Notes Verify motor starting requirements of 3-S0P-0D4A will be met for 35 FCU. Given in Initial Conditions Comment: Procedure Step 4.2.1 ..J 4. Performance Step: Standard:

Verify that the Fan Cooler Filter Unit Normal Inlet Dampers (A and 8) for 35 Fan Cooler Unit are OPEN. Rotate CONT. RECIRC. UNIT NO. 35 FLOW VLV 1305 switch to OPEN. Observe Green Light OFF and red light ON. PaneISBF-2 Comment: Procedure Step 4.2.2 30f9 Performance Information (Denote critical steps with a check mark ;J) "5. Performance Step: Standard:

Verify that the Fan Cooler Filter Unit Normal & Incident Damper (Bypass Damper C) for 35 Fan Cooler Unit is OPEN. Rotate CONT. RECIRC. UNIT NO. 35 FLOW VLV 1306 switch to OPEN. Observe Green Light OFF and red light ON. Observe Containment Control Recirc Air Unit Valve Tripped alarm clear PaneISBF-2 Comment: Procedure Step 4.2.3 6. Performance

7. Performance Standard:

Review NOTE before step 4.2.4 Reviews NOTE Verify that the Fan Cooler Filter Unit Incident Damper (Damper D) for 35 FCU is CLOSED. Observe CONT. RECIRC. UNIT NO. 35 FLOWVLV 1307 switch in CLOSE and Green Light is ON Panel SBF-2 Comment: Procedure Step 4.2.4 4of9 Performance Information (Denote critical steps with a check mark ;/) Performance Step: Verify that the FCU starts by monitoring the current on the associated 480V bus.

Observe 480V bus amps for bus 6A Panel SHF CUE: A Spare RO will standby and observe bus 6A amps when the fan is started.

Procedure Step 4.2.5 ..J 9. Performance Review NOTE before step 4.2.5 Reviews NOTE Comment: 10. Performance Start 35 Fan Cooler Unit Rotate Containment Recirc Fans Switch for 35 FCU to START. Observe green light OFF and Red Light ON Panel SBF-2 CUE: The spare RO reports and increase and then decrease in bus 6A amps.

Procedure Step 4.2.6 The CONTAINMENT RECIRC FAN MOTORS BEARING VIBRATIONS alarm on SBF-1 is expected to annunciate.

Candidate should acknowledge this alarm 50f9 Appendix Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) Performance Step: If CONTAINMENT RECIRC FAN MOTORS BEARING VIBRATIONS alarms, THEN RESET the alarm using the reset pushbutton on Panel SBF-1 Depresses pushbutton on Panel SBF-1 Observer the alarm resets. Comment: Procedure Step 4.2.7 Terminating Cue:

Complete 6of9 Appendix C Page 7 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:

Result: SAT or Examiner's signature and date: __________7of9 Appendix C Simulator Setup Form ES-C-1 This JPM can be run from virtually any simulator Initial Condition Ensure that 35 FCU is secured Ensure Dampers AlB and C are closed for 35 FCU 80f9 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The plant is at indicated power

• 31 -34 Containment Fan Cooler Units (FCU) are in operation

• Breaker Maintenance is scheduled for 32 FCU

• Containment Temperature is 87.5 0

• Service Water is properly aligned to all FCUs

• All Precautions and Limitations have been satisfied

• 35 FCU was secured 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago for breaker maintenance

• Motor Starting Frequency requirement have been verified.

Initiating Cue: You are the BOP and the CRS has directed you to start 35 Fan Cooler Unit in accordance with 3-S0P-CB-010.

---

Appendix C Job Performance Measure Form ES-C-1 Facility:

Indian Point 3 Task No: 0800060331 Task Title: Energize Buses 5 and 6 from 13.8 KV Power 062000A401 KiA

Reference:

RO -3.3 SRO -3.1 Job Performance Measure No: SIM F Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance x Classroom Simulator X 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 plant is at approximately 45% power.

• The Station Service Transformer experienced a fault

• The operating crew entered of 3-AOP-138KV

-1.

• 13.8KV power is available.

• 6.9 KV Bus 5 Lockout Relay 86ST5 is reset

• 6.9 KV Bus 6 Lockout Relay 86ST6 is reset Task Standard:

6.9 KV buses 5 and 6 are energized from 13.8KV source Required Materials:

None General

References:

3-AOP-138KV-1 Attachment 1 Initiating Cue: You are the BOP and the CRS has directed you to re-energize Buses 5 and 6 from 13.8KV in accordance with steps 1.10 through 1.30 in 3-AOP-138KV-1, Attachment

1. Time Critical Task: No 1 of 12 Appendix C Job Performance Measure Form ES-C-1 Validation Time: 15 Minutes 2 of Form Performance Information (Denote critical steps with a check mark ...J) '" 1. Performance Place the 6900V bus tie breaker in PULL OUT.

Place the following in pullout: o 6900V Bus No. 1-5 Tie in PULLOUT o 6900V Bus No. 2-5 Tie in PULLOUT o 6900V Bus No. 3-6 Tie in PULLOUT o 6900V Bus No. 4-6 Tie in PULLOUT Panel SHF Comment: Procedure Step 1.10 2. Performance Will 6.9 KV Bus 5 be energized from 13.8KV source?

YES -Given in Initiating Cue Comment: Procedure Step 1.11 '" 3. Performance Place 35 Circ Water Pump breaker in PULL OUT CCR control switch placed in PULL OUT for 35 Circ Water Pump PanelSJF Comment: Procedure Step 1.12 3 of 12 Performance Information (Denote critical steps with a check mark ;/) '" 4. Performance Step: Is 6900KV bus No.5 Normal Feed breaker in Pullout? Place 6900KV bus No.5 Normal Feed breaker in Pullout Standard:

6900V Bus No.5 Normal Feed breaker control switch placed to PU LL OUT PanelSHF Comment: Procedure Step 1.13 5. Performance Step: Is 6.9KV Bus 5 lockout relay 86ST5 reset? Standard:

YES. Given in Initial Conditions Candidate may contact the Nuclear Plant Operator to verify 86STS reset at the 6.9KV switchgear.

CUE: IF NPO contacted, report 86ST5 is reset Comment: Procedure Step 1.14 6. Performance Step: Is Station Service Transformer Supply Breaker 5 open and flag matched to green?

Observes green and amber lights ON and switch flag red. Rotate switch to TRIP then back to AUTO Panel SHF Comment: Procedure Step 1.15 4 of 12 Appendix Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/> 7. Performance Step: Is voltage zero on 6.9KV bus 5 Standard:

YES. Places 6900V Bus Voltmeter switch to Bus 5 position and verifies 6900V Bus meter indicates zero. Panel SHF Comment: Procedure Step 1 . 16 '" 8. Performance Step: Close GT-35 6.9 KV Bus No.5 Feed Breaker Rotate Breaker Control Switch from Pullout to Close position.

Observes Green Light OFF and Red Light ON PanelSHF Comment: Procedure Step 1.17 9. Performance Is 6.9KV Bus 5 energized?

YES. Observes voltage indicated on 6900V Bus Voltmeter.

Panel SHF Comment: Procedure Step 1.18 10. Performance Is Bus 5A Normal Feed breaker open?

YES. Observes Gree Light ON. The flag is still RED. The candidate may rotate the switch to TRIP to match the flag position with breaker position.

Panel SHF Comment: Procedure Step 1 . 19 5 of 12 Appendix Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J) 11. Performance Step: Close Sta. Serv Trans. 5 Supply Breaker SS5 Standard:

Rotate Switch to CLOSE position.

Observe Green Light OFF and Red Light ON.

Procedure Step 1.20 This step in not critical because it is not necessary to energize bus 5. It is a step necessary to energize 480V bus 5A. 12.. Performance Bus 6 be energized from 13.8KV source?

YES -Given in Initiating Cue Procedure Step 1.21 "13. Performance Place 34 Circ Water Pump and Standby Circ Water Pump breakers in PULL OUT CCR control switch placed in PULL OUT for 34 and Standby Circ Water Pump PanelSJF Procedure Step 1.22 6 of 12 Appendix Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ") "14. Performance Step: Is 6900KV bus No.6 Normal Feed breaker in Pullout? Place 6900KV bus No.6 Normal Feed breaker in Pullout Standard:

6900V Bus No.6 Normal Feed breaker control switch placed to PULL OUT Panel SHF Comment: Procedure Step 1.23 15. Performance Step: Is 6.9KV Bus 6tockout relay 86ST6 reset? Standard:

YES. Given in Initial Conditions Candidate may contact the Nuclear Plant Operator to verify 868T6 reset at the 6.9KV switchgear.

CUE: IF NPO contacted, report 86ST5 is reset Comment: Procedure Step 1.24 Performance Step: Is Station Service Transformer Supply Breaker 6 open and flag matched to green?

Observes green and amber lights ON and switch flag red. Rotate switch to TRIP then back to AUTO Panel8HF Comment: Procedure Step 1.25 7 of 12 Appendix Page 8 Form ES-C-1 Performance Information (Denote critical steps with a check mark -../) 17. Performance Step: Is voltage zero on 6.9KV bus 6 Standard:

YES. Places 6900V Bus Voltmeter switch to Bus 6 position and verifies 6900V Bus meter indicates zero. Panel SHF Comment: Procedure Step 1.26 -../ 18. Performance Close GT-36 6.9 KV Bus No.6 Feed Breaker Rotate Breaker Control Switch from Pullout to Close position.

Observes Green Light OFF and Red Light ON Panel SHF Comment: Procedure Step 1.27 19. Performance Is 6.9KV Bus 6 energized?

YES. Observes voltage indicated on 6900V Bus Voltmeter.

Panel SHF Comment: Procedure Step 1.28 20. Performance Is Bus 6A Normal Feed breaker open?

YES. Observes Green Light ON. The flag is still RED. The candidate may rotate the switch to TRIP to match the flag position with breaker position.

Panel SHF Procedure Step 1.29 8 of 12 Appendix Page 9 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/> 21. Performance Step: Close Sta. Serv Trans. 6 Supply Breaker SS6 Standard:

Rotate Switch to CLOSE position.

Observe Green Light OFF and Red Light ON.

Procedure Step 1.30 This step in not critical because it is not necessary to energize bus 6. It is a step necessary to energize 480V bus 6A. Terminating Cue: JPM Complete 9 of 12

Appendix C Page 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Facility Number of Time to Question Result: SAT or Examiner's signature and date: _______________10 of 12 Appendix C Simulator Setup Form Reset Simulator to IC24 Insert Malfunction MAL EPS006 Place Simulator in Run and let conditions stabilize.

Perform the first 17 steps of AOP-138KV-1 11 of 12 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The plant is at approximately 45% power.

• The Station Service Transformer experienced a fault

• The operating crew entered of 3-AOP-138KV-1.

• 13.8KV power is available.

• 6.9 KV Bus 5 Lockout Relay 86ST5 is reset

• 6.9 KV Bus 6 Lockout Relay 86ST6 is reset Initiating Cue: You are the BOP and the CRS has directed you to re-energize Buses 5 and 6 from 13.8KV in accordance with steps 1.10 through 1.30 in 3-AOP-138KV-1, Attachment

1.

---

Appendix C Job Performance Measure Form ES-C-1 Facility:

Indian 3 Task No: 0390120431 Task Title: Respond to a Steam Flow Channel Failure 035000K401 KIA

Reference:

RO -3.6 SRO -3.8 Job Performance Measure No: SIM G Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance x Classroom Simulator X 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 measure will be Initial

• The reactor is at indicated power

• Steady State, equilibrium Xenon conditions exist

• No equipment is out of service Task Standard:

Stable plant Required Materials: General

References:

Initiating Cue: You are the ATC. Take appropriate actions to stabilize Time Critical Task: Validation 10f9

_A-L.Jpp'-e_n_d_ix_C

_________... _P_ag""_e_2

___.________F_o_rm_E_S_-C_-1_

Performance Information (Denote critical steps with a check mark ;/) 2. Performance Check All Control Systems

• Rod Control -Not Affected

• PRZR Pressure Control-Not Affected

• PRZR Level Control -Not Affected

• MBFP Speed Control Not Affected

• SG Pressure Control Not Affected

• SG Level Control -IS AFFECTED All above indications are located on the Flight Panel Check indications for all controls systems -Only Steam Flow is affected.

This is part of the immediate actions step 3.1 for 3-AOP-INST-1.

The candidate should check all of these indication from memory. When conditions are stable the candidate should obtain the procedure and evaluate the control systems again. 20f9

______ Page Form ES-C-1 Performance Information (Denote critical steps with a check mark --J) 3. Performance Step: Has an instrument failure occurred?

Standard:

YES Operator determines FT-449B has failed low. Panel FBF Comment: Procedure Step 4.1 4. Performance Got to the applicable step for the indicated failure. Step 4.70 for Steam Flow Failure Operator determines step 4.70 is the correct step from the table Comment: Procedure Step 4.2 Performance Step: Are both SG Transfer Switches selected to the affected channel.

YES. However, the Steam Flow Transfer Switch did not transfer control to the non-affected channel. Operator may attempt to transfer again. Panel FBF Comment: Procedure Step 4.3 30f9 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 7. Performance Step: Return controls for unaffected equipment used to stabilize plant conditions to auto as desired. Standard:

No equipment can be returned to auto. Comment: Procedure Step 4.72 8. Performance Step: Refer to the following TS tables for required actions

• 3.3.1-1

• 3.3.2-1 Standard:

No Action Required Comment: Procedure Step 4.73 CUE: The STA will evaluate Tech Specs. 4 of 9 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ."f) 9. Performance Step: Standard:

Comment: 10. Performance Step: Standard:

Observe CAUTION before Step 4.74 Reviews Caution Are all redundant bistable status lights for failed instruments listed in Attachment 4 Table 1 extinguished Check each of the listed status lights OFF

• H-19 --8G 34 LO LEVEL LC447G

• 1-7 --HI 8TM FLOW LP31 FC419A

• J-7 --HI 8TM FLOW LP31 FC419B

• 1-8 --HI 8TM FLOW LP32 FC429A

• J-8 --HI 8TM FLOW LP32 FC429B

• 1-9 --HI 8TM FLOW LP33 FC439A

• J-9 --HI 8TM FLOW LP33 FC439B Comment: Procedure Step 4.74 11. Performance Step: Observe NOTE before step 4.75 Standard:

Reviews Note Comment: 50f9 Appendix Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) ..J 12. Performance Step: Trip bistables for failed instrument listed in Attachment 4 Table 2 Standard:

Locate rack White A-8 Place the switches listed below in the tripped (Up) postion

• Loop 48, High SF 51

• Loop 48, SF > FWF Comment: Procedure Step 4.75 Performance Step: Are all bistable status lights for failed instrument listed in Attachment 4 illuminated?

At panel SOF verify status lights are illuminated.

Comment: Procedure Step 4.76 Terminating Cue: JPM Complete 6of9 VERIFICATION OF COMPLETION Job Performance Measure No, Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Result: SAT or Examiner's signature and date: __________70f9 Appendix C Simulator Setup Form ES-C-1 Reset Simulator to any 100% Power IC Insert Malfunction MAL-MSS004H to 0% (NO Ramp time or Delay time) Insert Switch Override SWI-PCS007 to ON (Prevents contacts from transferring) 8 of9 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The reactor is at indicated power

• Steady State, equilibrium Xenon conditions exist

• No equipment is out of service Initiating You are the ATC. Take appropriate actions to stabilize

---

Appendix Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point 3 Task No: 0730150101 Task Title: Adjust R-27 Process Radiation Monitor Setpoints 073000A402 KIA

Reference:

RO -3.7 SRO -3.7 Job Performance Measure No: Sim H Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance X Actual Performance X Classroom Simulator X 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:

Plant startup is in progress.

Post maintenance testing is complete on R-27. A new alert setpoint has been provided by chemistry.

All requirements for setpoint control and log keeping have been met and are being performed by the CRS Task New alert setpoints entered into Bantam 11 and RM-23A for rad monitor R-27 Required Materials:

None General 3-S0P-RM-008, Radiation Monitoring Control Cabinet (BANTAM 11/RM23A Cabinet. Initiating Cue: You are the BOP and the CRS has directed you to adjust the Bantam-11 to 3.5E+3 per 3-S0P-RM-008, Radiation Monitoring Control Cabinet steps 4.3.5.1 Time Critical Task: No 1 of 8 Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 10 minutes 2 of 8 Performance Information (Denote critical steps with a check mark ..J) Performance Step: Refer to 3-S0P-RM-010 Radiation Monitor Setpoint Control 3-S0P-RM-010 requirements verified to be met Given in Initial Conditions All requirements for setpoint control and log keeping have been met and are being performed by the eRS. Comment: Procedure Step 4.3.5.1 '\J 2. Performance Select Bantam 11 RM-27 channel per section 4.3.1 This can be accomplished several ways. From the Group Display enter 4027 then press SEL and verify RM-27 is backlit From the Group Menu press SEL button repeatedly until RM-27 is backlit From Grid Display select grid 1 and enter 4027 then press SEL and verify RM-27 and verify channel is backlit. From the Grid Display press SEL repeated until RM-27 is backlit Comment: Procedure Step 4.3.5.2 '" 3. Performance Select Channel Items display by depressing the Channel Items pushbutton.

Depresses Channel Items Pushbutton Comment: Procedure Step 4.3.5.2.a 3 of 8 Performance Information (Denote critical steps with a check mark -,J) "4. Performance Step: Insert Key and turn Normal Supervisor Switch to Supervisor Standard:

Insert and Rotate Key to Supervisor position Comment: Procedure Step 4.3.5.2.b "5. Performance If changing Alert Set point Then enter 010 press SEL and verify channel item is backlit properly enters numbers and presses SEL, then verifies channel is backlit Comment: Procedure Step 4.3.5.2.d-e " 6. Performance Enter new set point Enter setpoint in the following format 35 + 0 3 Comment: Procedure Step 4.3.5.4 4 of 8 Appendix Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) '" 7. Performance Step: Verify desired value is displayed If correct press Enter Standard:

Observe display and depress Enter if correct. If not correct press Clear and repeat step 4.3.5.4 Comment: Procedure Step 4.3.5.5 '" 8. Performance Turn Normal Supervisor keyswitch to NORMAL and REMOVE key.

Rotate switch to NORMAL and Remove Key Comment: Procedure Step 4.3.5.6 9. Performance Restore normal All Monitors display Depresses Group Menu Pushbutton then 026 and SEL to restore normal display Comment: Procedure Step 4.3.5.7 Terminating Cue: JPM Complete 50f8 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:

Result: SAT or Examiner's signature and date: __________6of8 Appendix C Simulator Setup Form ES-C-1 No Simulator Setup is necessary for this JPM 7 of Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

Plant startup is in progress.

Post maintenance testing is complete on R-27. A new alert setpoint has been provided by chemistry.

All requirements for setpoint control and log keeping have been met and are being performed by the CRS Initiating Cue: You are the BOP and the CRS has directed you to adjust the Bantam-11 to 3.5 E+3 per SOP-RM-008, Radiation Monitoring Control Cabinet steps 4.3.5.1.

---

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point Task No:

Task Title: locally Emergency 000024A104 Job Performance KIA

Reference:

RO -3.6 SRO -3.7 No: In-Plant Examinee:

NRC Facility Evaluator: Method of Simulated Performance x Actual Classroom Simulator Plant READ TO THE I will explain the initial conditions, which steps to simulate or discuss, and initiating cues. When you complete the task successfully, the objective for this performance measure will be Initial

• The Control Room has been evacuated due to a fire

• Source Range N-38 is on scale but count rate has not been decreasing as expected

• MCC-36A is energized, MCC-36B is de-energized

• 31 BA TP had been in-service

• Seal injection is in service to ALL Task Standard:

Local Emergency Boration has been established for 35 minutes per AOP-SSD-1, Attachment Required General

References:

2-AOP-SSD-1, Attachment 8, Emergency Boration -Initiating Cue: You are the ATC and the SM has directed you to Emergency Borate RCS in accordance with 3-AOP-SSD-1!

Attachment Time Critical Task: Validation Time: 20 1 of 9 Appendix Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 1. Performance Step: Obtain correct procedure Standard:

Obtains 3-AOP-SSD-1 Attachment 8 This procedure would have been picked up from the APP R cage outside the Unit 3 Control Room upon evacuation.

Comment: 2. Performance Step: Verify 31 BATP energized from MCC-36A Standard:

Locate breaker for 31 BATP on MCC-36A and verify it is closed. (Can also be locally verified if pump liS) Comment: Procedure Step 8.1 CUE: Breaker on MCC36A is CLOSED Performance Step: Determine if 32 Boric Acid Transfer Pump energized at MCC-36B?

Determine 32 Boric Acid Transfer Pump cannot be energized.

MCC-36B is de-energized

-Given in Initial Conditions.

Comment: Procedure Step 8.2 Performance Step: Determine that 31 Boric Acid Transfer Pump be used to supply blender? Standard:

Given in Initial Conditions Comment: Procedure Step 8.3 CUE: If requested the SM directs you to use 31 Boric Acid Transfer Pump. 20f9 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/> 5. Performance Step: Open CH-360 (31 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER). Standard:

Locate CH-360 and determines valve is open Comment: Procedure Step 8.4. This step in NOT critical because if 31 BATP was in service, this valve would be opened. Depending on actual plant configuration this valve may be opened or closed. CUE: Valve is Open 6. Performance Step: Close CH-370 (32 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER). Standard:

Locate CH-370 and determine valve is closed Comment: Procedure Step B.5. This step in NOT critical because if 31 BATP was in service, this valve would be closed. Depending on actual plant configuration this valve may be opened or closed. CUE: Valve is Closed 7. Performance Step: Close CH-267B (31 BORIC ACID FILTER BYPASS ISOLATION FROM 32 BORIC ACID TRANSFER PUMP) Standard:

Locate CH-267B and determine valve is closed Comment: Procedure Step 8.6. This step in NOT critical because if 31 BATP was in service, this valve would be closed. Depending on actual plant configuration this valve may be opened or closed. CUE: Valve is Closed 30f9 Appendix Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) :.J 8. Performance Step: Close CH-HCV*105 and CH-HCV-105 (Boric Acid Transfer Tank Recirculation Flow Controllers)

Standard:

Locate valves. Isolate air supply to the valves and vent the air from the diaphragm.

Comment: Procedure Step 8.7 CUE: Valves are closed Performance Step: Depress clutch lever for CH-MOV-333 (EMERGENCY BORATION VALVE). (PAB 73' el. Boric Acid Blender area) Standard:

Locate valve and depress clutch lever. Comment: Procedure Step 8.8 CUE: Lever moves down freely Performance Step: Engage clutch by moving handwheel as necessary and release clutch lever.

Rotate handwheel as necessary until clutch engages and then release lever Comment: Procedure Step 8.9 CUE: Handwheel rotates slightly and clutch is engaged Performance Step: Open CH-MOV-333 by rotating handwheel counterclockwise.

Attempts to rotate handwheel counterclockwise.

Comment: Procedure Step 8.10 CUE: Handwheel will NOT rotate 40f9 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,j) Transfer control of aligned Boric Acid Transfer Pump to LOCAL at the boric acid transfer pumps. Standard:

Place hand switch for 31 BATP in Local Comment: Procedure Step 8.11 CUE: Switch rotates to Local Position '" 15. Performance Step: Place aligned Boric Acid Transfer Pump Speed Switch to FAST. Standard:

Locate switch and rotate to Fast Speed Comment: Procedure Step 8.12 CUE: Switch is in Fast Position 5 of9 Performance Information (Denote critical steps with a check mark >/> 16. Performance Step: Determine that Seal Injection flow to all RCPs was NOT isolated Standard:

Given in Initial Conditions.

Goes to Procedure Step 8.15 Comment: Procedure Step 8.13 Performance Step: Dispatch Nuclear NPO to monitor RCP Seal Injections Flows Directs Nuclear NPO to monitor Rep Seal Injection Flows Comment Procedure Step 8.15 CUE NPO Acknowledges direction.

18. Performance Step: Observe NOTE before Step 8.17 Standard:

Reviews NOTE Comment: CUE: 35 minutes has elapsed. 6of9 Appendix Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,J) <;J 19. Performance Step: Increase Charging Pump Speed until each RCP Seal Injection indicates 10 -12 gpm Standard:

Locate Charging Pump Controls Establish communication with the Nuclear NPO Rotate speed potentiometer for operating charging pump Stop adjustment when NPO reports Seal Injection flow is 10 -12 gpm on all pumps Comment: Procedure Step 8.16 Charging Pump Controls are located in a cabinet by the entrance to the charging pump cells. CUE: NPO reports all RCP seal injection flows indicate 10 -12 gpm Performance Step: WHEN boration has been ongoing for> 35 minutes, THEN stop Boric Acid Transfer Pump.

Rotate Boric Acid Transfer Pump switch to STOP Comment: Procedure Step 8.17 CUE: Pump is stopped Terminating Cue: ..IPM Complete 7of9 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:

Result: SAT or Examiner's signature and date: __________8of9 Appendix Initial Conditions Form ES-C-1 Initial Conditions: The Control Room has been evacuated due to a fire Source Range N-38 is on scale but count rate has not been decreasing as expected MCC-36A is energized, MCC-36S is de-energized 31 SA TP had been in-service Seal injection is in service to ALL RCPS Initiating Cue: You are the ATC and the SM has directed you to Emergency Borate the RCS in accordance with 3-AOP-SSO-1, Attachment

8.

--Control Room Inaccessibility Safe 3-AOP-SSD-1 Rev 14 Shutdown Control Page 113 of 195 Attachment 8 Emergency Boratlon -Local Page 1 of 5 ACTION/EXPECTED RESPONSE _Is 31 Boric Acid Transfer Pump energized at MCC-36A (7RH)? _Is 32 Boric Acid Transfer Pump energized at MCC-36B (7RH)? _Will 31 Boric Acid Transfer Pump be used to supply blender? _Open CH-360 (31 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER). _Close CH-370 (32 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER). _CloseCH-267B (31 BORIC ACID FILTER BYPASS ISOLATION FROM 32 BORIC ACID TRANSFER PUMP) RESPONSE NOT OBTAINED Energize 31 Boric Acid Transfer Pump at MCC-36A (7RH). Energize 32 Boric Acid Transfer Pump at MCC-36B (7RH). Open CH-370 (32 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER). 2._Close CH-360 (31 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER). 3._Close CH-267A (31 BORIC ACID FILTER BYPASS ISOLATION FROM 31 BORIC ACID TRANSFER PUMP) 4._GO TO Step 8.7.

Control Room Inaccessibility Safe 3-AOP-SSD-l Rev 14 Shutdown Control Page 11 5 of 195 Attachment 8 Emergency Boratlon

• Local Page 3 of 5 ACTION/EXPECTED RESPONSE Close the following valves: _CH-HCV-105 (31 BORIC ACID STORAGE TANK RECIRCULATION FLOW CONTROLLER SETTING) _CH-HCV-104 (32 BORIC ACID STORAGE TANK RECIRCULATION CONTROLLER _Depress clutch lever for CH*MOV-333 (EMERGENCY BORATION VALVE). (PAB 73' el. Boric Acid Blender area) _ Engage clutch by moving handwheel as necessary and release clutch lever. _Open CH*MOV-333 by rotating handwheel counterclockwise. _Transfer control of aligned Boric Acid Transfer Pump to LOCAL at the boric acid transfer pumps. _ Place aligned Boric Acid Transfer Pump Speed Switch to FAST. RESPONSE NOT OBTAINED 1. _ Secure and bleed off both air supplies to CH-FCV*110A (BORIC ACID BLENDER BORIC ACID FLOW CONTROL VALVE). 2._0pen CH*293 (BORIC ACID BLENDER BORIC ACID BYPASS ISOLA TION).

Control Room Inaccessibility Safe 3-AOP-SSD-l Rev 14 Shutdown Control Page 117 of 195 Attachment Emergency Boratlon

• Page 5 of 5 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _Was Seal Injection to all RCPs _ GO TO Step 8.15 isolated due to no Charging and CCW Pumps running? _GO TO Step 8.17. Dispatch Nuclear NPO to monitor RCP Seal Injection Flows: _FI-144 (RCP #31 SEAL WATER FLOW INDICATOR)

_FI-143 (RCP #32 SEAL WATER FLOW INDICATOR)

_FI-116 (RCP #33 SEAL WATER FLOW INDICATOR)

_FI-115 (RCP #34 SEAL FLOW m_____ .m_...

• _'ncrease charging pump speed until each RCP Seal Injection indicates 10

• 12 gpm. NOTE u> 35 minutes" is a minimum value and is not intended to specify the exact amount of boration. Clock starts after seal injection flow is established. _WHEN boration has been ongoing for> 35 minutes, THEN stop Boric Acid Transfer Pump. EXIT this attachment.

• • • END ....

---

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point 3 Task No: 0840050432 Task Title: Perform Actions for RHR Pump Cooling using City Water 005000K101 KIA

Reference:

RO..,.. 3.2 SRO -3.1 Job Performance Measure No: In Plant 2 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance x Actual Performance Classroom Simulator Plant x 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 measure will be Initial

• The unit is in Mode 5 with #31 RHR pump in service.

• The CCW supply to the RHR pumps has failed.

• City Water is available for 31 RHR Pump. Task Standard:

Backup City Water aligned to the 31 RHR Pump and draining to the floor Required Materials:

None General

References:

3-S0P-ESP-001, Initiating Cue: You are the Spare RO and the CRS has directed you to align Normal Backup City Water to cool 31 RHR Pump per SOP-ESP-001, Section 4.12. Time Critical Task: No Validation Time: 20 Minutes 1 of 7 Appendix Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) 1. Performance Step: Obtain Correct Procedure Standard:

Obtains 3-S0P-ESP-001, Local Equipment Operation and Contingency Actions. Comment: 2. Performance Step: Observe Cautions before Step 4.12.1 Standard:

Reviews Cautions Comment: ..J 3. Performance Close AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation Locates Valve, Simulates rotating in the clockwise direction The Valve is Closed Comment: Procedure Step 4.12.1.1 2 of 7 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J 4. Performance Step: Standard:

CUE: Close AC-737 A, CC Return from 31 RHR Pump Thermal Barrier Inlet Isolation Locates Valve, Simulates rotating in the clockwise direction The Valve is Closed Comment: Procedure Step 4.12.1.2 ..J 5. Performance Step: Standard:

CUE: Close AC*1871 D, CC Supply to 31 RHR Seal HX Inlet Isolation Locates Valve, Simulates rotating in the clockwise direction The Valve is Closed Comment: Procedure Step 4.12.1.2 '\I 6. Performance Step: Standard:

CUE: INSTALL emergency city water supply jumper (e.g., hose) between MW*18*16, Hose Connection Isolation, (across from filter room on column) and one inch tee located immediately downstream of AC.736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation Jumper hose located in spare RHR pump cell, hose connection locations identified, and simulate connection actions. Jumper Hose is connected.

Comment: Procedure Step 4.12.1.4 3 of 7 Appendix Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;J) 7. Performance Step: INSTALL drain hose on % inch tee located immediately downstream of AC-1871D, CC Supply to 31 RHR Pump Seal Hx Inlet Isolation(31 RHR pump room) Standard:

% inch tee located and simulated hose connection actions CUE: Hose is connected Comment: Procedure Step 4.12.1.5 8. Performance Step: Route drain hose to suitable drain Standard:

Drain hose routed Drain Hose is routed to drain Comment: Procedure Step 4.12.1.6 '" 9. Performance OPEN AC-1871C, CC Return from 31 RHR Pump Seal Hx Outlet Isolation (31 RHR pump room).

Valve located, locking screws backed out or removed and valve simulated opened (counterclockwise) Locking Screw is removed and valve is Open Comment: Procedure Step 4.12.1.7 40f7 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ..J 10. Performance Step: OPEN MW-18-16, Hose Connection Isolation (across from filter room on column) Standard:

locate valve and simulate rotate counterclockwise (Open) CUE: Valve is Open Comment: Procedure Step 4.12.8 Terminating Cue: JPM Complete 50f7 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:

Result: SAT or UNSA Examiner's signature and date: __________60f7 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The unit is in Mode 5 with #31 RHR pump in service.

• The CCW supply to the RHR pumps has failed.

• City Water is available for 31 RHR Pump. Initiating Cue: You are the Spare RO and the CRS has directed you to align Normal Backup City Water to cool 31 RHR Pump per SOP-ESP-001, Section 4.12.

LOCAL EQUIPMENT OPERATION No: 3-S0P-ESP-001 Rev: 22 AND CONTINGENCY ACTIONS Page 38 of63 4.12 31 RHR Pump Cooling Using City Water CAUTION Without cooling water, two RHR pumps may be run for a maximum of 45 minutes followed by a single pump run for an additional maximum of 45 minutes (Ref. 5.2.6). Only 31 RHR pump can be supplied by City Water, as an emergency-cooling source. IF CCW can NOT be established AND it is directed to operate 31 RHR pump, THEN PROVIDE backup City Water supply as follows:

CLOSE AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation.

CLOSE AC-737 A, CC Return from 31 RHR Pump Thermal Barrier and Seal Hx Outlet Isolation.

CLOSE AC-1871 D, CC Supply to 31 RHR Pump Seal Hx Inlet Isolation.

INSTALL emergency city water supply jumper (e.g., hose) between MW-18-16, Hose Connection Isolation, (across from filter room on column) and one inch tee located immediately downstream of AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation.

INSTALL drain hose on % inch tee located immediately downstream of AC-1871 D, CC Supply to 31 RHR Pump Seal Hx Inlet Isolation{31 RHR pump room).

ROUTE drain hose to a suitable (e.g., 31 RHR Pump Room floor OPEN AC-1871C, CC Return from 31 RHR Pump Seal Hx Outlet Isolation (31 RHR pump room).

OPEN MW-18-16, Hose Connection Isolation (across from filter room on column). WHEN city water cooling to 31 RHR pump is no longer required, THEN PERFORM the following:

CLOSE MW-18-16, Hose Connection Isolation (across from filter room on column).

LOCAL EQUIPMENT OPERATION No:

Rev: 22 AND CONTINGENCY ACTIONS Page 39 of 63 REMOVE jumper hose installed between MW-18-16, Hose Connection Isolation, and one inch tee downstream of AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation, and REPLACE cap on tee.

REMOVE jumper hose installed downstream of AC-1871D, CC Supply to 31 RHR Pump Seal Hx Inlet Isolation, and REPLACE cap on tee.

OPEN AC-1871D, CC Supply to 31 RHR Pump Seal Hx Inlet Isolation.

OPEN AC-737A, CC Return from 31 RHR Pump Thermal Barrier and Seal Hx Outlet.

THROTTLE AC-1871C to achieve 7.5 gpm as read on FIC-646.

THROTTLE AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation, to obtain 15 gpm total flow as read on FIC-646. 4.13 Emergency City Water Supply to the AFW Pumps OPEN the applicable AFW Pump suction supply:

• CT-PCV-1187, 31 ABFP City Water Makeup Isolation

• CT -PCV-1188, 32 ABFP City Water Makeup Isolation

• CT-PCV-1189, 33 ABFP City Water Makeup Isolation IF unable to open City Water suction supplies THEN have Maintenance open the valves using ELC-004-FIR (Appendix uRI! Repair). 4.14 Restore from Emergency City Water Supply to the AFW Pumps IF ELC-004-FIR, (Appendix uRn Repair) was used to perform sect. 4.13, THEN COORDINATE with maintenance to restore condition to normal. CLOSE the applicable AFW Pump suction supply:

• CT-PCV-1187, 31 ABFP City Water Makeup Isolation

• CT-PCV-1188, 32 ABFP City Water Makeup Isolation

• CT-PCV-1189, 33 ABFP City Water Makeup Isolation

---

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:

Indian Point 3 Task No: 0710040134 Task Title: Release a Gas Decay Tank KiA

Reference:

RO -2.6 SRO -2.6 Job Performance Measure No: In Plant 3 Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance Classroom Simulator Plant x 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 measure will be Initial

• The release of 31 Small Gas Decay Tank is complete

• 32 Small Gas Decay Tank must be released.

• RCV-014 is closed

• An Independent Verifier (IV) is standing by Task Standard:

Required Materials:

None General

References:

3-S0P-WDS-013, Gaseous Waste Releases Initiating Cue: You are the Nuclear NPO and the SM directs you to complete the restoration lineup for 31 Small Gas Decay Tank (SGDT) and perform the Release Alignment for 32 SGDT in accordance with 3-S0P-WDS-013 Attachment

9. Time Critical Task: No 1 of 7 Appendix C Job Performance Measure Form ES-C-1 Validation Time: 2of7 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ") '" 1. Performance Step: Standard:

CUE: Comment: '" 2. Performance Step: Standard:

CUE: Comment: Perform restoration section of applicable Attachment 9 for 31 Small Gas Decay Tank Obtains Attachment 9 Locates and Simulates Closing WD-1652A (Rotate Clockwise)

Valve is Closed Perform valve alignment to isolate tank and prepare to sample per Attachment

9. Locate each valve on list below and check or reposition valve Only WD-1652 is critical, the remaining valves are expected to be in the indicate position The valves are in the position indicated WD-1652B is OPEN 3 of?

---

Appendix C VALVE NUMBER WD-1641 B WD-1642B WD-1651B WD-1676B WD-1652B WD-1652A WD-1652C WD-1652D WD-1652E WD-1652F WD-1617 WD-1618 WD-1619 WD-1620 CUE: Pagel 4 VALVE DESCRIPTION REQUIRED POSITION N2 Supply to 32 SGDT Isolation CLOSED 32 SGDT Drain (1) CLOSED 32 SGDT Fill Isolation (1) CLOSED PT -1053 Root Isolation OPEN 32 SGDT to Release Header Isolation OPEN 31 SGDT to Release Header Isolation CLOSED 33 SGDT to Releasl: Header Isolation CLOSED 34 SGDT to Release Header Isolation CLOSED 35 SGDT to Release Header Isolation CLOSED 36 SGDT to Release Header Isolation CLOSED 31 LGDT to Release Header Isolation CLOSED 32 LGDT to Release Header Isolation CLOSED 33 LGDT to Release Header Isolation CLOSED 34 LGDT to Releasta Header Isolation CLOSED The valves are in the position indicated WD-1652B is OPEN Form ES-C-1 Appendix C Page 5 Form ES-C-1 3. Performance Step: Initiate Independent Verification (IV) of gas decay tank release path per Attachment 9 Standard:

Contact another individual to peliorm independent verification.

Independent Verifier is standing by on radio. Given in Initial Conditions.

CUE: Acknowledge as Independent Verifier and report that IV is complete.

Comment: Terminating Cue: JPM Complete 50f7 6 Form VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Result: SAT or Examiner's signature and date: __________6 of 7 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The release of 31 Small Gas Decay Tank is complete

• 32 Small Gas Decay Tank must be released.

• RCV-014 is closed

• An Independent Verifier (IV) is standing by Initiating Cue: You are the Nuclear NPO and the SM directs you to complete the restoration lineup for 31 Small Gas Decay Tank (SGDn and perform the Release Alignment for 32 SGDT in accordance with 3-S0P-WDS-013 Attachment

9.

Appendix Scenario Outline Facility:

IPEG Unit 3 Scenario No . 1 Op-Test No.: 1 Examiners:

Operators:

Initial Conditions:

100% power steady state. 32 AFW Pump is out of service for bearing repair. Need to have 35 SWP in service. Turnover:

32 AFW Pumps is expected back in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Team has been asked to reduce power to 90% for a Turbine Stot;! and Control Valve Test. Event No. Malt. No. Event I Type* Event Description 1 N/A R (ATC) Perform power reduction.

N (BOP, CRS) 2 CFW013 E C (CRS) C (ATC) 33 MFRV fails open in auto -manual available.

33 MFRV will be placed in manual to control 33 SG level. 3 CFW011 C (ALL) NRHX Tube Leak. 4 EPS05B C (CRS, BOP) Loss of 480V Bus 3A. 34 or 36 SWP will be started. TS (CRS)

• CRS will determine T.S. shutdown is required due AFW pumps. 5 N/A R (ATC) Perform power reduction with Feed Reg Valve in Manual N (BOP, CRS) 6 MAL-C (CRS) Inadvertent main generator trip. Reactor will not automatically trip. GEN002 Manual trip will be required.

C (ATC) I i7 MAL-M (ALL) 33 AFW pump will not start causing a loss of heat sink. Heat sink will be restored using condensate.

C MAL-TS (CRS) PORV 455C leaks by requiring isolation.

CRS can be asked about PRS003 TS requirements at end of scenario.

C (ATC) D * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor U3 NRC Scenario 1 Power ReductIon fro 100%,33 MFRV Falls Open -Manual Control AvaIl. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, paR v 455C Leaks requiring isolation.

Page 1 of20 Appendix Scenario Outline Form ES-O-1 The evaluation begins with the plant at 100% power steady state operation. 32 ABFP has been out-of-service for bearing oil line repair for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. It is expected back within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (TS 3.7.5 -72 hr AOT). 31 and 33 ABFPs are protected equipment. The team has been requested to reduce power to 90% in preparation for a turbine stop and control valve test. After the team has begun reducing reactor power, 33 Main Feed Regulating valve (FCV-417) fails open. The team will take actions per AOP-FVIJ-1, "Loss of Feedwater" and place the MFRV in manual to control SG level. During subsequent actions of AOP-FW-1, a leak develops in the Non-Regen heat exchanger.

The team will respond per AOP-CVCS-1 and isolate Letdown. While putting in Excess Letdown, an electrical fault occurs on 480\1 Bus 3A. The team will have to start an essential service water pump per AOP-480V-1.

The CRS will determine that two AFW Pumps are inoperable necessitating a shutdown per T.S. 3.7.5 or safety function determination per 3.0.6. The team will commence a power reduction in accordance with POP-2.1 with 33 Main Feed Regulating Valve in Manual. The MTG will then trip inadvertently.

The reactor will not trip automatically and will require manual trip at the flight panel. After the trip, 33 AFW Pump will not start, and one of the PORVs begins to leak by creating an isolable SBLOCA. The team will respond to the PORV failure by closing its block valve. The team will initiate performance of E-O, "Reactor Trip or Safety Injection".

Since no motor-driven AFW pump is available, the team will transition to FR-H.1, "Loss of Secondary Heat Sink" due to inadequate AFW flow. The scenario will terminate when Condensate flow is established to the SGs Procedure Flowpath:

AOP-FW-1, AOP-CVCS-1, AOP-480V-1, E-O, FR-H.1 Critical Tasks are as follows: E-O -A Manually trip reactor from the CCR before completing E-O, Step 1 E-O -M Close block MOV upstream of stuck-open Pzr PORV by completion of the first step in the ERG network that directs the crew to close the block MOV FR-H.1 -A Establish Condensate or Main Feed flow to at least one SG before 3 out 4 SG WR levels < 20% U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip AvaiL, 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 2 of20 Appendix Scenario Outline Form ES-O-1 -Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES I IC Reset Simulator to IC-11 SES Insert malfunction MAL-Auxiliary Feedwater Pump 31 Failures CFW001A to TRIP Insert malfunction MAL-Auxiliary Feedwater Pump 32 Trip CFW001B Insert override SWI-A TSOO2A Green Lamp Aux Feedwater Pump No. 32 to Off Control Switch Module Insert override SWI-ATS002B Red Lamp Aux Feedwater Pump No. 32 Control to Off Switch Module Insert override SWI-ATS002C Trip Pos Aux Feedwater Pump No. 32 Control to On Switch Module Insert override SWI-ATS002D On Pos Aux Feedwater Pump No. 32 Control Switch Module Insert remote LOA-MSS021 MS-41 S/G 32 To AFWP Iso to 0 Insert remote LOA-MSS022 MS-42 S/G 33 To AFWP Iso to 0 Insert malfunction MAL-Auxiliary Feedwater Pump 33 Failures CFW001 C to TRIP Insert override SWI-PCV-455C Red Lamp Pressurizer Relief Valve RCS021B to Off PCV-455C Control Switch Create event 30 JPPLP4(1)==1 -desc Set trigger 30 to actuate after reactor trip Insert malfunction MAL-FDW CNTRL FIC-437 Auto Mode Failure CFW013E to 100.00000 on (Manual Avail) event 1 Insert malfunction MAL-Non-Regenerative Letdown Heat Exchanger CFW013E to 50.00000 on Tube Leak event 2 Insert malfunction MAL-Main Generator Trip GEN002 on event 4 Insert malfunction MAL-Loss Of 480 V Bus 3A EPS005B on event 3 Insert malfunction MAL-Pressurizer Relief Valve 455C Valve Position PRS003C after 60 to Failure 10.00000 on event 30 Insert malfunction MAL-Reactor Trip Breakers Fail To Open (Auto RPS002A to ALL_FAIL Failure) I U3 NRC Scenario I Power Reduction fro J 00%, 33 MFRV Fails Open Manual Control A vail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip -Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 30[20 Appendix Scenario Outline Form ES-D-1

• SES Setup Load Schedule and verify . Schedule malfunctions and overrides have been Floor Setup Perform Setup Checklist Ensure 35 Service Water Pump Update Protected Equipment Hang Danger on 32 AFW pump PC Risk is Yellow Hang Protected Equipment Tags For: 31 and 33 AFW pumps Event 1

• Respond as requested by Crew performs power reduction crew . Event 2 Activate Trigger 1 when MAL-CFW013E 33 SG MFRV Fails Open directed Role Play Acknowledge requests for 18.C will develop a troubleshooting plan I&C to troubleshoot Event 3 Activate Trigger 2 MAL-CFW013E NRHX Tube Leak

• Role Respond as requested by the LOA-CVC031 Open/adjust CH-409, 33 charging crew pump recirc valve Event Activate Trigger 3 MAL-EPS005B Fault on bus 3A Role Play I If asked to investigate bus 3A i Bus has smell of ozone and probably tripped on actual fault. More troubleshooting will be required Event Respond as requested by Power reduction due to INOPERABILITY of crew AFW Event 6 Activate Trigger MAL-GEN002 Inadvertent Generator MAL-RPS002A Reactor fails to trip manual trip is MAL-PRS003C PORV starts to leak by can manuall::

isolated using block i lay Respond as requested by the I crew Event 7 Inserted at MAL-CFW001 B 33 AFW pump failure to start Role Play Respond as requested by the If asked to investigate 33 AFW pump report the pump is mechanically bound and will not rotate. As Nuc NPO stand by MCC36A1B to open breakers for BFO-2s Insert LOA-CFW066 and LOA-CFW067 to DEENERGIZE when requested II Event Inserted 30 seconds after MAL-PRS003D PORV 455C leak set to 10% reactor trip U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip -Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 4 of20 Appendix Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: Event No.: _1_ Event

Description:

Power Escalation Time Applicant's Actions or Behavior Note: The reactivity plan for the power reduction should be developed by the team in the briefing room prior to taking the watch. The plan could call for boration and/or rod insertion CRS Assigns roles for power reduction ATC Reviews reactivity ATC If rods are

• Places/verifies rods are in Manual

• Inserts rods specified number of steps Observes:

0 Proper rod motion 0 Tavg 0 Power BOP Peer rod ATC If boration is

• USing SOP-CVCS-003

• Places RCS Makeup control to Stop

• Place RCS Mode selector to borate

• Adjusts integrator to desired boration amount

• Places RCS Makeup control to Start Observes:

0 Proper makeup response 0 Tavg 0 Power BOP Peer check boration U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 5 of20 Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: _1_ Event

Description:

Power Escalation Time I Position Applicant's Actions or Behavior Lead Evaluator When the following has been demonstrated/observed:

• Sufficient load ascension,

• Sufficient normal plant operations by the BOP . Then instruct Booth to insert Event 2. U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control AvaiL NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 6 of20 Appendix Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: Event No.: l Event

Description:

Time Position ! Examinee's Actions or I -. ATC Diagnose 33 MFRV failing open

• Feed Flow to 33 SG increasing

• 33 SG Level Increasing

• Steam Generator Level Control Deviation Alarm I I Refers to ARPs for alarms !

33 MFRV in Manual Control and adjusts manual setpoint to lower feed flow . to lower level i I Directs crew to perform immediate operator actions of 3-AOP-FW-1 performs IOAs of AOP-FW-1

• Checks status of Main Boiler Feed Pumps (MBFP) _ .. i

• Announce IOAs complete CRS Announces Entering 3-AOP-FW-1 and begins reading individual steps. Identify both MBFPs operating Determines transition to step 4.54 I I CRS May perform a Crew Brief at this I Shift Manager that failure has occurred.

CRS/ATC Determine Main Feed Regulating Valve (MFRV) has failed open. I Reports MFRV is in manual and control is functioning.

SG level is returning to program.

• CRS/ATC Check status of additional feed system valves -all normal I Notifies the System Engineer that MFRV needs to be inspected U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 7 of20 Appendix D Scenario Outline Form ES-D-1 . Op-Test No.: _1_ Scenario No.: Event No.: .L Event

Description:

Time I Position Examinee's Actions or Behavior Notifies 8M I Lead Examiner Direct Booth to initiate Event U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open -Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip -Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 8 of20 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: L Event

Description:

Time Examinee's Actions or Behavior Identify Loss of Letdown/Increase in CCW Surge Tank Level I BOP CRS Enter Continue with Loss of I CRS/ATC

• Determine there is a bubble in the BOP Close CH LCV 459 and CH-LCV-460 (Panel SF I CRS/ATC i Determines Seal Injection exist Transition to 4.20 BOP/ATC Coordinate shutting CH-HCV-142 maintaining discharge header pressure < 2650 psig ATC Adjust charging pump speed to maintain seal injection approximately 6 gpm CRS i Direct NPO to throttle CH-409 (33 Charging Pump Recirculation Valve) as necessary.

I Booth Oe.e,.ator If directed to throttle 409 LOA-CVC031 CRS Determines excess letdown is dl3sired directs BOP to perform Attachment 2 I BOP I Notify HP that -excess letdown will be placed in service BOP Contact Nuc NPO to verify status of RCDT BOP Open the following valves

• AC-AOV-793 (Panel I

• AC-AOV-796 (Panel

• AC-AOV-791 (Panel SNF) I

• AC-AOV-798

{panel SNF} I BOP Check CH-HCV-123 Closed (Panel SFF) I ii U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open -Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 9 of20 Appendix Scenario Outline Form Op-Test No.: _1_ Scenario No.: Event No.: Event

Description:

Time Examinee's Actions or Behavior BOP i Verify CH-AOV-215 in Divert (Panel SFF) BOP Open the following CH-AOV-213A (Panel *

• CH-AOV-213B

{panel SFF} BOP Slowly Open CH-HCV-123 (Panel SFF) i BOP When sufficient warm-up (slow rise on TI-122)

• Close CH-HCV-123 (Panel

• Place CH-AOV-215 to NORMAL (Panel .... ** Throttle 0een CH-HCV-123

{Panel SFF} Lead Examiner . Direct Booth Operator to initiate Event 4 i U3 NRC Scenario I Power Reduction fro 100%, 33 MFRV Fails Open -Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 10 of20 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: Event

Description:

-Time Position Examinee's Actions or Behavior CRS/BOP Multiple alarms -Diagnose Loss of Bus 3A CRS Enter AOP-480V-1 -CRS/BOP Determine power is lost to Bus 3A and RHR was not in service . CRS/ATC Determine 33 Charging Pump is running Determine 2 CCW Pumps are running Determine Essential Service Water Header Pressure is < 60 psig and no SW pumps are operating on the Essential SW Headerr .

• Start 34 or 36 SW CRSIA TC I Determine Turbine is on line I CRS/ATC Determine Power has not been lost to IRPI -Determine Vacuum NOT decreasing BOP Determine ISO PHASE BUS RETURN AIR HIGH TEMP alarm is clear ---------Determine waste release is NOT in progress I . ------_.Dispatch operator to monitor EDGs Determine IRPI is operable Initiate Review of Tech Specs ----ICRS Determine that 2 AFW pumps are inoperable necessitating a shutdown per T.S. 3.7.5 --

U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open -Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip -Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page II 01'20 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: I Event I 1 Time J Examinee's Actions or Behavior Booth Operator If necessary call as SM and direct the crew to initiate the shutdown i The unit should be off the line in 4 CRS I Obtain POP _2.1 and SM permission for power reduction CRS Use Attachment 3 from POP-2.1 for power reduction CRS I Record power reduction data and contact the SM to make required notifications i I l I I CRS , Direct ATC/BOP to perform a Reactivity Calculation for the power reduction ATC/BOP Prepare Reactivity Calculation using the Daily Reactivity Sheet, OPT -25 I I CRS Assigns roles for power reduction ATC Reviews reactivity plan I ATC If rods are inserted:

• Places/verifies rods are in Manual

• Inserts rods specified number of steps Observes:

0 Proper rod motion 0 Tavg 0 Power BOP 11l:>I::ILlUII U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip -Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 1201'20 Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.:

Time Examinee's Actions or Behavior ATC If boration is performed: Energize All Pressurizer Heaters Places RCS Makeup control to Stop Place RCS Makeup Mode selector to borate Adjusts integrator to desired boration amount Places RCS Makeup control to Start* Observes:

0 Proper makeup response 0 Tavg 0 Power BOP Peer check boration ATCIBOP Initiate Turbine Load Reduction at desired rate Governor (Preferred) Load Limit 1 I

• Load Limit 2 ATC Maintain the manual setpoint for the MFRV Controllers Nulled. ATC Adjust Control Rod Position per TS and Graph-RPC-16 lead Evaluator When the following has been dEimonstrated/observed: Sufficient load reduction.

• Sufficient normal plant operations by the BOP. il Then instruct Booth to insert Event 6. U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 13 of20 Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: Event Descri 'on: Time Position Examinee's Actions or Behavior CRS/ATC Diagnose Turbine Trip with failure of reactor to trip Announce "Tripping the Reactor" then depress the' reactor trip button on the Flight Panel NOTE The CRS may direct tripping the reactor before the ATC makes the announcement. When Unit trips, direct team to p1arform immediate actions of E-O

• Verifies immediate actions using the procedure.

When the CRS directs "Perform the Immediate Operator Actions of E-O", the A TC and BOP will first perform the IOAs silently only announcing unexpected conditions.

The crew will then re-perform the IOAs verbalizing each item. Verifies Reactor Trip: (Panel FCF)

• Reactor trip and bypass breakers open

• Rod bottom lights lit

• IRPls < 20 steps

• Nuclear flux d ATC Verifies Turbine Trip by observing stop valves closed (Panel FAF) Check status of 480V buses (Panel Observe SA, 2A, and 6A busses energized from Offsite Check SI Determine SI is

• Any SI Annunciator

-Lit (Panel FDF)

• Panel SBF-1 SBF-2 U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open -Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip -Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 14 of20 Appendix D Scenario Outline Form ES-D-1 ATC Determines SI NOT actuated and NOT required; however, RCS pressure will be decreasing.

After the "Silent Pass" through the IOAs it is permissible to perform Prudent Operator Actions. This includes closing the PORV Block valve. If the ATC and CRS have diagnosed the leaking PORV, then the PORV Block Valve should be closed at this time. This is Event 8. If the PORV leak is NOT diagnosed then the crew will continue.

BOP/ATC Check AFW Status

• Observes Total of all SG flow indicators IS NOT> 686 gpm CRS Transition to ES-O.1 il II CRS Transition to FR-H.1 due to loss of all AFW U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open -Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip -Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 15 of20 Appendix D Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: Event No.: Event Time Position Examinee's Actions or Behavior ATC Diagnose leak by from PORV 45!5C

• Pressurizer PORV and Safety Acoustic Monitoring Annunciator

• Pressurizer Relief Line High Temp Annunciator

• Acoustic Monitor ATC Announce Closing Block Valve for PORV-455C then close the valve. The CRS may direct closing the PORV Block Valve (535) before the A TC makes the above announcement ATC Verify PORV Block Valve closed and leakage is stopped. U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 16 of20 Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: 1 Event No.:-1. Event

Description:

Time Examinee's Actions or Behavior CRS/ATC Determine if Heat Sink is required Check RCS Pressure>

any non-faulted SG pressure (Panel FBF/FDF)

• Check RCS Temperature>

350°F (Panel CRS/BOP Check if Bleed and Feed is Average of the 3 lowest wide range SG Levels < 20% (Panel SCF) This is NOT expected at this CRS/BOP Prepare to establish AFW Check SG Blowdown isolation and sample valves closed(Panel SCF) Check CST Level> 3 Feet Check valves CT-6 & 64 Open (Panel sCFL___________-l i CRS/BOP Establish AFW Flow using Motor Driven Pumps Check 480V power available Bus 3A or 6A energized Check Motor Driven Pups both running o Start motor driven AFW Pumps

• If unable to start either motor driven AFW Pump, Close is SG Aux Feed Reg Valves (FCV-406A-406D) If both motor driven AFW pumps are unavailable Go to Attachment

________________________________

n CRS/BOP Determine that 32 AFW Pump is NOT available Determine 32 AFW Pump NOT running (Tagged Out) Determine 32 ABW Pump Overspeed Trip Valve Closed alarm (Panel SKF) is actuated due to tag out ______+!________+-___*__

____.________________________I CRS/ATC Stop all RCPs CRS/ATC Try to establish Feedwater flow to any SG BOP

• Check Condensate Pump Power Supplies Available o 6.9 kV buses 1, 2, 4 energized (Panel SHF) Go To Attachment 3 to establish feedwater from secondary source. U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 17 of20 Appendix Scenario Outline Form ES-O-1 Op-Test No,: _1_ Scenario No,: _1_ Event No,: J.. Event DescripJion:

Time Examinee's Actions or Behavior CRS/ATC Check if a low pressure water source is BOP

• Check any condensate pumps running (Panel Check only one condensate pump running o Secure all by one condensate pump Check MBFPs any running

• o Cannot Reset and Start 1 MBFP CRS/BOP Block Automatic SI Actuation Check SI NOT Actuated

• Place SI block key switches to DEFEAT (Panel SBF-2) CRS/BOP Check Condensate Pump only feed source CRS/ATC Depressurize at least ONE SG to less than 380 psig to establish feed flow, Manually dump steam using atmospherics from at least one SG at maximum rate CRS/BOP Dispatch NPO to MBFP discharge valve breakers Role play Respond as NPO Standing By at MCC 36A and MCC 36B CRS/ATC Prepare to Align BOP

• Place MFRVs in manual and close (Panel Ensure Bypass FRVs Closed (Panel FBF) Place Feedwater Isolation Defeat key switches in DEFEAT Obtain keys from key locker 1/FW1DA (Rack G4) o 1/FW1DB (Rack: CRS/ATC Reset BOP

• Check SI Check verification of SI Automatic Actions of step 2 -12 of RO-1 completed If BOP available perform steps 2 -12 of RO-1 o Press both SI Reset buttons on panel SBF-2 i o Check SI Reset -SI Actuated lights extinguished U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control AvaiL NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip -Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 180[20 Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.:...J..

Event Time Examinee's Actions or Behavior Establish Initial FW conditions BOP Ensure Bypass MOVs open BFD-MOV-90-1

-BFD-MOV-90-4 (Panel SCF) Ensure Main Feedwater MOVs Open BFD-MOV-5-1

-BFD-MOV-5-4 Crack Open Bypass Feedwater FRVs FCV-417L FCV-427L FCV-437L o CRS/ATC Place Steam Flow and Feed Flow Recorders to Steam Flow switches on FBF (Red)

• Feed Flow switches on CRS/ATC Align Feedwater Manually close MBFP Recirc Valves Align MBFP Discharge Valves Open BFD-MOV-2-31/32 When valves are Open, direct NPO to open discharge valve breakers on MCC 36A and MCC 36B . Booth Operator Insert LOA-CPW066 and LOA-CFW067 to DEENERGIZE and valves rlA** AnArl1fi71l,rl Control bypass feedwater FRVs to rapidly resptore at least one SG Narrow Range Level to > 9% Control Low Flow Bypass valves Lead

• Terminate the Scenario when adequate feedwater flow is established.

U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip A vaiL, 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 19 of20 Appendix 0 Scenario Outline Form ES-D-1 Post Scenario Event Classification Event Classification

-Alert EAL 1.1.1 Failure of an Automatic trip signal to reduce power range < 5% AND Manual Trip is successful NOTE: The following event classification is possible depending on plant conditions when scenario is terminated.

Event Classification

-Site Area Emergency RED PATH in FO.3 Heat Sink AND Feed and Bleed is required.

U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 20 of20 Appendix 0 Scenario Outline Form ES-D-1 Facility:

Indian Point 3 Scenario No.: _2_ Op-Test No.:_1 Examiners:

Operators:

Initial Conditions:

Reset simulator to 9% Load Simulator Schedule-Scellari02 The Plant is in Mode 1 just above 9% power preparing to come on line.

Raise power to approximately 12% to place MTG in service. No equipment is out of service .... . Event Event No. No. Type* Description 1 N/A R(ATC) Power ascension, maintain SG levels in manual. N(CRS) N(BOP) 2 C(CRS) 31 CCW Pump trip with failure of 32 to auto start. SWSOO7 C(BOP) TS(CRS) 3 I(ALL) Controlling PZR Pressure transmitter fails high. RCS028 A TS(CRS) 4 C(CRS) FCV-625 spurious closure. CCWOO 8 C(BOP) M(ALL} Steam leak in the Turbine leading to plant trip. 33 MSIV SGNOO5 fails to close. 6 C(ALL} Entered at setup, Reactor Trip Breakers will not open causing PPLOO3! team to enter FR-S.1. 4 7 C(BOP) Entered at setup, AFW will not auto-start requiring manual action CFWOO1 in FR-S.1 AlC 8 C(CRS) Entered at setup, SI does not automatically actuate. Manual PPL4871 8 C(BOP} actuation will be required.

• {N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG. Page I of 17 Session Outline: The scenario begins with the plant at 9% power with no equipment is out of service. The team has been instructed to raise power to approximatl91y 12% and place MTG in service. After taking the watch, the crew will commence raising power. After the power escalation has progressed, 31 CCW Pump will trip and 32 CCW Pump will fail to auto-start.

The team will start 32 CCW pump per ARP-010. Following the restoration of CCW, a failure high of PT-455 will occur. The team will respond using AOP-INST-1 "Instrument or Controller Failures." The channel will be removed from service. After the channel is removed from service, FCV-625 will go closed with no apparent reason. The team should respond per ARP-01 0 and re-open the valve. If the team elects to not re-open the valve, the scenario may continue.

Prior to completion of the Subsequent Actions of AOP-CCW-1, a steam break will occur in the turbine building.

The team will attempt to manually trip the plant but the reactor trip breakers will not open. The reactor will not trip from the Control Room and the team will respond per FR-S.1 , "Response to Nuclear Power Generation I ATWS," and will shutdown the reactor by manually inserting control rods and initiating Emergency Boration.

The reactor trip breakers will be locally opened after an NPO is dispatched.

33 MSIV will fail to close from the control switches.

The Team will also determine that SI did not automatically actuate and must manually actuate SI. The team will proceed through FR-S.1 until transition to E-O, "Reactor Trip or Safety Injection." After the transition to E-O is made, the team will determine that three SGs are intact and 33 SG is faulted. The team will transition to E-2, Faulted Steam Generator Isolation and isolate 33 SG. At this point the scenario is terminated.

Procedure flow path: POP-1.3, ARP-010, AOP-INST-1, ARP-010, AOP-UC-1, E-O, FR-S.1, E-O, E-2 Critical Tasks: CT-1 Insert negative reactivity into the core by at least one of the following methods before completing FR-S.1 step 4:

• De-energize the control rod drive MG sets

• Place rod control in manual and insel1 RCCAs

• Establish emergency boration flow to the RCS. CT -2 Establish at least 686 gpm AFW flow to the SGs before completion of FR-S.1 step 3. CT-3 Manually actuate at least one train of SIS actuated safeguards before completion of E-O step 4. U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT -455 Failure, FCV -625 Closure, Steam Line Rupture, A TWS, Faulted sa. Page 2 of 17 I Simulator Setup and Instructor Directions , Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSEIINSTRUCTOR CUES I IC Use IC for NRC Scenario 2 Reset Simulator to 9% power Ie 9% Power Starting SES Setup Run Schedule and verify Loads Reactor Trip Breaker Schedule malfunctions and Loads Auto 51 Failure have been entered Loads MS Isolation failure Carefully walk boards and Loads 32 CCW Pump Autostart failure check for items like Turbine Loads 31/33 AFW Pumps Autostart failures and FWH alarms that may be Loads 31 CCW Pump failure on Trigger 1 distractions to candidates.

Loads PT-455 failure on Trigger 2 Loads FCV-625 failure on Trigger 3 I Loads Turbine Hall Steam Leak on Trigger 4 Floor Setup Perform setup checklist Event 1 Respond as performs power . i Event 2 Trigger 1 when When directed by the Lead Evaluator, activate Trigger 1 to cause 31 CCW Pump to trip. MAL-CCW001A to TRIP Role Play If called to check 31 and 32 3'1 CCW Pump Motor has slight acrid odor. CCWPumps Breaker tripped on over-current.

The pump that was started is operating with no issues . . 32 CCW Pump, Motor, and Breaker all aQQear normal I Event 3 Actuate Trigger 2 when When directed by the Lead Evaluator, activate Trigger 2 to cause PT-455 to fail high with a 60 second ramp. MAL-PRS005A to 2500 with 60s ramp Role If I&C is contacted about Report back that a troubleshooting package PT -455 failure will be prepared Event Actuate Trigger 3 vVhen directed by the Lead Evaluator, activate Trigger 3 to FCV-625 to fail closed. At lead evaluator direction SWI-CCW010C to On AS SOON AS GOES ACTIVATE TRIGGER TO REMOVE OVERRIDE L __I U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SO. Page 3 of 17 i Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES Role Play I When Nuclear NPO Nuke NPO reports that flow at FIC-625 dispatched normal after valve is Actuate Trigger 4 VVhen directed by the Lead Evaluator, activate Trigger 4: At lead evaluator Insert MAL-MSS009A to 6650000 in 600 direction Role Play If NPO dispatched to look If NPOs are dispatched to look for steam, for steam leak report back that a large steam leak exists at the north end of the turbine hall. Role NPO cannot locally trip If trigger does not work, remove overrides reactor until Emergency preventing reactor trip. May have to insert Boration is commenced.

manual reactor trip Actuate Trigger 30 to U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT 455 Failure, FCV -625 Closure, Steam Line Rupture, A TWS, Faulted SO. Page 4 of 17 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: ...L Event No.: Page _1_of .1 Event

Description:

Power Ascension Time Applicant's Actions or Behavior Note: The reactivity plan for the power ascension should be developed by team in briefing room prior to taking the watch. The plan could call for dilution and/or rod withdrawal. Assigns roles for power ascension Reviews reactivity plan If rods are withdrawn:

• Places/verifies rods are in Manual

• Withdraws rods Observes:

0 Proper rod motion 0 Tavg 0 Power Peer checks rod withdrawal If dilution is performed:

• Places ReS Makeup control to Stop

• Place ReS Makeup Mode selector to Dilute

• Adjusts integrator to desired dilution amount

• Places ReS Makeup control to Start Observes:

0 Proper makeup responsEi 0 Tavg 0 Power Peer check dilution Adjust Low Flow Feed Reg Valves to maintain SG levels. U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT -455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG. Page 5 of 17 Appendix 0 Required Operator Actions Form Lead Evaluator When the following has been demonstrated/observed:

• Sufficient load ascension.

• Sufficient normal plant operations by the BOP. Then instruct Booth to insert Event 2. U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SO. Page 6 of 17 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: Event No.: -.l... PageEvent

Description:

31 CCW Pump trip Time Position Applicant's Actions or Behavior BOP Observes CCW Pump Discharge Alarms and only 33 CCW Pump running BOP Recommends/announces starting 32 CCW Pump BOP May refers to ARP 3-ARP-10 CRS Concurs with recommendation or orders 32 CCW Pump start BOP Starts 32 CCW Pump CRS May enter AOP-CCW-1 CRS Refers to T.S. 3.7.8 and TRM 3.7.B and determines plant is in a 30 Day AOT Lead Evaluator After CRS has evaluated TRMITS. have Booth initiate Event 3 U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS" Faulted SO. Page 7 of17 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: L Event No.: -L Page_1_of Event

Description:

Controlling PZR Pressure transmitter fails high Time Position BOP ATC Applicant's Actions or Behavior PZR Hjgh Pressure Channel Trip and PZR Hjgh Pressure alarms Diagnose PZR Pressure instrument failure based on above and Spray Valves opening Announces and places Master Pressure Controller in Manual CRS Instructs team to perform immediate operator actions of AOP-INST-1 ATC Checks all instrumentation listed in AOP-INST-1 for failures Announces immediate operator actions complete CRS Announces entry into AOP-INST-1 Re-checks all instrumentation with ATC Verifies PZR pressure is in Manual CRS BOP BOP Directs BOP to defeat PT -455 in pressure control circuit and delta-t circuit In Rack B-6 places P/455A in Defeat 1 & 4 In Rack B-8 places T/4111A in Defeat Loop 1 ATC Switches recorder to an operable channel ATC Returns Master Pressure Controller to Auto CRS Refers to T.S. Table 3.3.1-1 Function 5 and 7 Table 3.3.2-1 Function 1 d and 7 Determines in 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AOT to trip bistables May have T.S. condition due to low PZR Pressure 3.4.1 Condition A Lead Evaluator Bistables do not have to be tripped. When T.S. evaluated instruct Booth to insert Event 4 U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT -455 Failure, FCV -625 Closure, Steam Line Rupture, ATWS, Faulted SG. Page 8 of 17

______R_e.quired Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.:..1.-Event No.: Page _1_of ..1 Event

Description:

FCV-625 spurious closure , Time Position Applicant's Actions or Behavior BOP Notes CCW Thermal Barrier Return Low Flow alarm ! BOP Observes FCV-625 has gone closed BOP Refers to ARP-01 0 Note: CRS should determine based on ARP guidance and indications that the closure was spurious and re-opening the valve is appropriate.

If the valve remains closed, the scenario can continue.

BOP Re-open FCV-625 BOP Direct Nuke NPO to monitor flow at FI-625 Lead Evaluator When valve is re-opened, or it is clear it will remain closed, instruct Booth to initiate Event 5. U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG. Page 9 of 17 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: -.L Event No.: i Page _1_of J. Event

Description:

Steam leak in the Turbine Building leading to plant trip. Time Position App,licant's Actions or Behavior ATC Diagnose Steam Leak:

• Power increase

• Tavg decrease

• Steam Flow increase

• SG Level increase CRS Implements AOP-UC-1 Directs crew to:

• Trip Reactor (Reactor does not trip)

• Close MSIVs (33 MSIV will not go closed)

• Go to E-O ! Proceed to Event 6 when CRS gives order to trip reactor U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, A TWS, Faulted SG. Page 10 of 17 Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: _1_ Scenario No.: Event No.: 6/7_ Page _1_of Event

Description:

Entered at setup, Reactor Trip Bneakers will not open causing team to enter S.1. Entered at setu AFW will not auto-start manual action in FR-S.1 Time licant's Actions or Behavior Will to tri reactor BOP Start 31 and 33 or 32 AFW Pumps establish 686 gpm BOP/ATC Initiate Emergency Boration:

• Verify Charging Pump running

• Open MOV

• Close HCV-104/10S

• Place both boric acid pumps in high speed and restart

• Place Charging Pump in manual

• Maximize char!ging pump speed At this point the Booth willi trip the reactor locally. U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT -455 Failure, FCV -625 Closure, Steam Line Rupture, ATWS, Faulted SO. Page 11 of 17 Required Operator Actions Form ES-D-2 Note: At this point or prior, the crew may attempt to close MSIVs. When 33 MSIV does not close, AFW should be secured to 33 SG. Also with the reactor tripped, the crew may back down on AFW flow. Op-Test No.: _1_ Scenario No.:..L Event No.: Page_1_of A Event

Description:

Entered at setup, SI does not automatically actuate. Manual actuation will be required.

Time icant's Actions or Behavior Recognize that SI should have actuated and is needed for Steamline delta-p Manually actuate SI May restart charging pump Perform Steps 35-42 of E-O:

• Verify SI Pumps Running

• Verify Fan Cooler Units Running, place dampers in SI position

• Open SW VaIVE!S for Containment Cooling

• Check Status of SI Valves, AFW, CCW. ESW, CIVs Verifies reactor trip:

• Reactor trip brE!akers open

• Neutron flux decreasing

• Rod bottom lights lit

• IRPls all < 20 Steps U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, A TWS, Faulted SG. Page 12 of 17 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: -L. Event No.: Page-L.of Event

Description:

Entered at setup, SI does not automatically actuate. lVIanual actuation will be required.

CRS/ATC CRS/ATC CRStATC CRSt CRS ATC ATC BOP ATC ATC/BOP Secure Emergency Boration

• Close MOV-333

• Place BATPs in slow

• Open HCV-104/105 to 25% Check RCP Seal Cooling (if charging was not started and FCV-625 was left closed, RCPs may be tripped at this point) Restore charging flow Verify SDM With SI. this is not necessary.

but the team may start a boration Transition to E-O Verifies Reactor Trip: (Panel FCF)

• Reactor trip and bypass breakers open

• Rod bottom lights lit

• IRPls < 20 steps Verifies Turbine Trip by ()bserving stop valves closed (Panel Check status of 480V buses (Panel Observe ALL busses energized from Offsite Check SI Determine SI is

• Any SI Annunciator

-Lit (Panel FDF)

• SI Pumps Any Running (Panel SBF-1, SBF-2) Manually Actuates SI U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT -455 Failure, FCV -625 Closure, Steam Line Rupture, ATWS, Faulted SG. Page 13 ofl7 Appendix Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: Event No.: Event

Description:

Entered at setup, SI does not automatically actuate. Manual actuation will required.

BOP/ATC CRS ATC ATC ATC ATC ATC ATC Check AFW Observes Total of all SG flow indicators>

365 gpm (Panel Controls feed flow to maintain SG levels 9 -Adjust flow control valve potentiometers Direct BOP to perform RO-1 BOP Operator Actions during use of EOPs Verify Feedwater Isolation Check Main Boiler Feed Pumps Tripped (Panel FAF) Check MBFP Discharge Valves Closed (Panel FAF) Check Feed Reg Valves and Bypasses Closedllsolated Main and Bypass MOVs Closed (Panel SCF) Main FRVs 2 is True (Panel SNF) Bypass FRVs (Panel FAF) Check Blowdown Isolation Valves Closed (Panel SCF) Verify SI Flow Check Pressure < 1700 psig (Panel FBF, or FDF) Check High Head Pump Flow Indicators (Panel SBF-2) Check Pressure < 360 psig (Panel FDF WR Press Recorder) Check RHR Pumps Flow Indicators (Panel SBF-2_ Verify Containment Spray NOT required Check Containment Pressure remained < 22 psig (Panel J01 or SBF-2) Check RCP Seal Cooling Bearing Coolant Low Flow Alarm Clear (Panel SGF) Thermal Barrier CCW Header Low Flow alarm Clear (Panel SGF) Establish Charging Flow U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG. Page 14 of 17

_A---L....pL-pe_n

__d_i_x_D___.___

Operator Actions ATC Check RCS Temperature ATC Check if RCPs should be stopped. RCPs may have been secured earlier. They will not be tripped at this step. ATC Check PORVs, Safety Valves, Sprays Closed Op-Test No.: Scenario No.: Event No.:

Event

Description:

Entered at setup, SI does not automatically actuate. Manual actuation will be required.

CRS/ATC Determine 33 SG is faulted CRS Announce entry into E-2 NOTE: E-2 contains the first specific steps to close MSIVs and isolate AFW flow to faulted SG. However, there is administrative guidance to take these actions ahead of E-2 steps. It is expected that these actions would have been taken either in FR-S.1 after the reactor being tripped locally or in E-O. If these actions have not been taken at this point, the scenario may continue to allow the team to take actions per Lead Evaluator Terminate Scenario U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, A TWS, Faulted SG. Page 15 of 17 Post Scenario Event Classification Event Classification

-Site Area EmergencyAh3rt EAL 1.1.2 RED path in Subcriticality and all attempts at tripping the reactor from the control room have failed to reduce power range < 5%. U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG. Page 16 of 17 DatelTime:

Today/Now Condition:

Plant Startup % Power: Xenon: Equilibrium RCS Boron: 1547 ppm Rods CB D -128 PZR Press Control: Channel 1 PZR Level Control: Channel 2 RCS Total Leakage: 0.1 gpm RCS Unidentified Leakage: 0.01 gpm Condenser Air leakage 6SCFM RCS Gas activity 1.78E-2 I-ICi/cc Risk Assessment:

Green Plant Equipment Plant is at 9% power with a startup in progress.

No equipment is out of Raise power to approximately 12% power and then warm up and place the in service. U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT -455 Failure, FCV -625 Closure, Steam Line Rupture, ATWS, Faulted sa. Page 17 of 17 Appendix Scenario Outline Form ES-O-1 1 Facility:

IPEC Unit 3 Scenario No.: Op-Test No.:

Operators:

Initial Conditions:

34% Power PORV 455C Leaks by seat -Block Valve 535 is Raise Power to Event Malf. No. Event No. Type" R (ATC) N/A Power Increase N N I MAL-Controlling Pressurizer Level Channel fails low TS (CRS) C MAL-PORV 456 leaks by seat. Close PORV Block Valve. C (CRS) PRS003 10 i I (ALL) 4 PT -412B failurE! causing AMSAC to be inoperable and requiring TS (CRS) TUR010 tripping of M MAL-Loop Flow Transmitter penetration failure C (BOP) 6 . 31 AFW Pump Trip C (CRS) MAL-SG Tube Leak to Rupture 32 SG I M (ALL) * (N)ormal, (R)eactivity, (I)nstrument (C)omponent, (M)ajor U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page I of33 Appendix 0 Scenario Outline Form ES-O-1 Session Outline: The evaluation begins with power is at 34% steady state. The crew will be directed to raise power to 100%. After adequate power change has occurred, Pressurizer Level Channel L T-460 will fail low resulting in a loss of letdown. The crew will respond in accordance with 3-AOP-INST-1, Instrument and Controller Failures.

The procedure will address both the instrumentationlTech Spec actions and restoration of charging and letdown. This is a Tech Spec for Instrumentation.

At lead examiner discretion, Pressurizer PORV 456 will start to leak past seat. The crew will attempt to close the PORV which will not be successful.

The crew will then close the motor operated block valve At lead examiner discretion, PT-4128 will fail low requiring bypassing AMSAC and tripping bistables.

This is a Tech Spec for Instrumentation.

At lead examiner discretion, 31 Loop Flow Transmitter Penetration will fail resulting in a small break LOCA The crew may respond using 3-AOP-LEAK-1.

The crew will likely trip the reactor and manually actuate Safety Injection.

Following the Safety Injection 31 AFW pump will trip on overcurrent.

This will require the crew to start 32 AFW pump to supply flow to 31 and 32 SG. The crew will proceed through E-O to E-1. When the crew enters E-1 a SGTR will occur in 32 SG. The crew will transition to E-3 when diagnostic check for SGTR or on Foldout page based on uncontrolled level increase.

The crew will perform actions in E-3. After the cooldown, the crew will not be able to use normal spray to depressurize the RCS. The crew will depressurize the RCS using the PORV. After depressurization actions the procedure checks 51 Termination Criteria and this will not be met (RCS pressure will not be stable or increasing) and transition to ECA-3.1due to LOCA with SGTR. The scenario will be terminated when the team demonstrates they control plant Cooldown or at the lead examiners discretion.

Procedure Flowpath:

POP-1.3, AOP-INST-1, ARP-FAF, AOP-INST-1, AOP-LEAK-1, E-O, E-1, E-3, ECA-3.1 Critical Tasks: CT-1 E-O-M Close block MOV upstream of stuck-open PZR PORV by completion of the first step in the ERG network that directs the crew to close the block valve. CT-2 Isolate feed to 32 SG prior to completion of E-3 Step 3. CT-3 Initiate RCS Cooldown of <100 °F/hr to SG overfill in ECA-3.1 U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 2 of33 i Appendix 0 Scenario Outline Form ES-O-1 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR IC Reset Reset Simulator to SES Setup Insert malfunction MAL-Schedule PRS006B to 0 on event 2 Insert malfunction PRS003D to 10.00000 in 60 on event 3 Insert malfunction TUR01 DB to 200.24899 on event 4 Insert malfunction RCSO 17 A on event 5 Insert malfunction CFW001A to TRIP on Insert malfunction SGN005B to 10.00000 on event 7 Insert override SWI-AIR002C to Off on event 30 Create Event 30 JPPLP4(1 }==1 -desc Set Trigger 30 to actuate i after Reactor SES Setup Load Schedule and Schedule malfunctions and have been Floor Setup Perform Setup Close PORV Block Valve , and hang CTO Risk is ????? Event 1 Respond as requested by the : crew i . Event 2 I Actuate Trigger 2 i Role Play I Acknowledge requests i I&C to Event 3 Activate trigger Role Play I Respond as requested by the crew EXPECTED RESPONSEIINSTRUCTOR CUES PRESSURIZER LEVEL CHANNEL 460 FAILURE PRESSURIZER RELIEF VALVE 456 VALVE POSITION FAILURE TURB FIRST-STAGE PRESS TRANS FAILURE (PT -412B) FAILURE OF FLOW TAP PENETRATION FT-414 AUXILIARY FEEDWATER PUMP 31 FAILURES STEAM GENERATOR 32 TUBE LEAK PCV-1228 OPEN POS INSTRUMENT AIR VLV NO. PCV-1228 CONTROL Actuate Trigger 30 when the Reactor Trips (which will then prevent 1228 from opening when attempted)

Hang CTO on PORV Block Valve 535 . Crew performs power ascension MAL PRS006B LT-460 fails low I&C will develop a troubleshooting MAL-PRS003D PORV 456 starts to leak by. U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 3 of33 i i Appendix 0 Scenario Outline Form ES-O-1 Event 4 Activate trigger 4 MAL-TUR10B PT-412B Fails low. Role Play

• Respond as requested by crew : Event 5 Activate Trigger 5 MAL-RCS017 A Failure of RCS flow tap. This is i

• a small Role Play Respond as requested by

• crew I Event 6 I Loaded at setup MAL-CFW001A Trip of 31 AFW Pump I Role Play

• Respond as requested by the I crew Event 7 : Activate Trigger 7 MAL-SGN005B Tube rupture in 32 SG . Role Play i Respond as requested by the ; I crew I I I U3 NRC Scenario 3 Power increase from 35%,LT*460 fails low Restore Letdown; PORV 456 leak, PT -412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 4 of33 Appendix Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: L Event No.: _1_ Event

Description:

Power Escalation Time Applicant's Actions or Behavior The reactivity plan for the power ascension should be developed by the team in the briefing room prior to takin! the watch. The plan could call for dilution and/or rod withdrawal Assigns roles for power Reviews reactivity If rods are withdrawn:

• Places/verifies rods are in Manual

• Withdraws rods

• Observes:

o Proper rod motion o Tavg o Power BOP Peer checks rod ATC If dilution is

• Places RCS Makeup control to Stop

• Place RCS Makeup Mode selector to Dilute

• Adjusts integrator to desired dilution amount

• Places RCS Makeup control to Start

• Observes:

o Proper makeup response o Tavg o BOP Peer check U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 5 of33 Appendix D Scenario Outline Form ES-D-1 ATe/BOP Lead Evaluator Initiate Turbine Load Increase at desired rate

• Governor (Preferred)

• Load Limit 1

• Load Limit 2 When the following has been demonstrated/observed:

• Sufficient load ascension.

• Sufficient normal plant operations by the BOP. Then instruct Booth to insert Event 2. U3 NRC Scenario 3 Power increase from 35%,L T-460 fails low Restore Letdown; PORV 456 leak, PT -412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 3 I AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 6 of33 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: Event Descri tion: Failure of Pressuriz_e_r_C'-o'-n tr_o_lI...... g_L_e_v-'-e_1 C.c--ha__n n-ce_I________________ in..... ..... Time ATC/BOP I i ATC . CRS i ATC i Examinee's Actions or Behavior Diagnose Failure of LT -460 Place 33 charging pump in Manual and stabilize pressurizer level. Direct Perform Immediate Operator Actions of AOP-INST-1 Silently evaluates for failure of control system inputs Rod 0 NIS Power 0 RCS 0 Turbine 1 st Stage

• Pressurizer Pressure Pressurizer Level 0 RCS MBFP Speed 0 Suction 0 Discharge 0 Steam Header SG Level 0 Steam 0 Steam 0 Feedwater SG Pressure 0 Atmospheric Steam 0 High Pressure Steam I i CRS/ATC Enter AOP-INST-1 and Re-perform IOAs verbalizing each input I U3 NRC Scenario 3 Power increase from 35%,L T -460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 7 of33 i Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: Event No.: Event

Description:

Failure of Pressurizer Controlling Level Channel Time Position Examinee's Actions or Behavior CRS/ATC Determine an Instrument failure has occurred.

CRS Identify section 4.105 of procedure CRS/ATC Determine the charging pump is in manual speed controlling pressurizer level in accordance with Graph RCS-2 CRS/ATC Determine channel has failed low CRS/BOP Place Ll460A LEVEL DEFEAT switch in DEFEAT CH 2 (RACK B-6 CRS/BOP Determine Letdown is isolated (LCV-459 is closed) (Panel SFF) CRS/BOP Close Orifice Isolation Valve (CH-AOV-200 A -C) (Panel SFF) CRS/BOP Place CH-PCV-135 Controller in MAN and adjust output to 50% (Panel SF F) CRS/BOP Place AC-TCV-130 Controller in MAN and adjust output to 50% (Panel SFF) CRS/BOP Determine CH-AOV-201 and 202 are OPEN (Panel SFF) CRS/BOP Determine CH-LCV-459 is closed and OPEN CH-AOV-459 and return to AUTO (Panel SFF) CRS/BOP Open ONE Orifice Isolation Valve (Panel SFF)

• CH-AOV-200A

• CH-AOV-200B

• BOP/ATC Coordinate to adjust charging flow as

• Charging pump speed (Panel FBF)

• Open HCV-142(Panel SFF)

• Close CH-409 (Local Action) U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 4561eak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 8 of33 Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: -.1.. Event No.: j::vent Failure of Pressurizer Controlling Lelvel Channel Time Position I Examinee's Actions or Behavior! i CRS/BOP IAdjust CH-PCV-135 as necessary to prevent flashing in the letdown line (Throttle

! closed to raise pressure to approximately 250 psig (Panel SF F) CRS/BOP Acljust AC-TCV-130 as necessary to maintain letdown temperature 100 -130°F ! CRS/ATC Place Modulating Heater switch to off for 5 seconds then Start and return to AUTO CRS/ATC Place control switch for Pressurizer Backup Heaters to OFF for 5 seconds then i return to auto. CRS/ATC Place one set of Backup Heaters to ON. NOTE: Heaters were in ON for dilution for : power ascension.

Crew may return all heaters to ON. CRS/ATC Determine if Pressurizer Level Recorder is selected to a Non-Affected Channel and . select an operable channel if necessary CRS Refer to Technical SpeCifications CRS Determines 0 TS 3.3.1-1 Function 8 AOT -6Hours 0 TS 3.3.3-1 Function 12 AOT 30 days 0 TS Basis 3.3.4 0 TRO 3.3.0.1 AOT 30 Dal's \ CRS/BOP Determine that NO redundant Bistable Status Lights are illuminated (Panel SOF) I ! CRS/BOP Trip Bistables for L T Rack White A-10 Bistable LOOP 2, High CRS/BOP Check Bistable Status Light for failed instrument Lead Examiner I nstruct the Booth to insert Event 3 , Tripping bistable has no impact on the remainder of the scenario.

Once Letdown is i restore, the scenario can proceed. U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak. PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 90f33 Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: --L Event No.: Event PORV 456 Leaks seat Time Position Examinee's Actions or Behavior ATC Diagnose leak by from PORV 456

• Pressurizer PORV and Safety Acoustic Monitoring Annunciator

• Pressurizer Relief Line High Temp Annunciator

• Acoustic Monitor ATC Announce Closing Block Valve for PORV-455C then close the valve. The CRS may direct closing the PORV Block Valve (536) before the A TC makes the above announcement Verify PORV Block Valve closed and leakage is stopped. U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 10 of33 Appendix Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: Event No.: Event

Description:

Turbine First StClge Pressure Transmitter Failure Low Time Position Examinee's Actions or Behavior ATCIBOP Diagnose Failure of PT-412B i CRS I Direct Immediate Operator Actions of AOP-INST-1 ATC Silently evaluates for failure of control system inputs Rod Control 0 NIS Power Range 0 RCS Temp 0 Turbine 1 st Stage Pressure Pressurizer Pressure Pressurizer Level Control

• RCS Temperature MBFP Speed Control 0 Suction Pressure 0 Discharge Pressure 0 Steam Header Pressure SG Level Control 0 Steam Pressure 0 Steam Flow 0 Feedwater Flow SG Pressure Control 0 Atmospheric Steam Dumps i 0 High Pressure Steam Dumps

• i CRS/ATC Enter AOP-INST-1 and Re-perform IOAs verbalizing each I CRS/ATC Determine an Instrument failure has occurred.

i CRS Identify section 4.172 of procedure i U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SaTR 32 SO, Steam Generator Tube Rupture with LOCA. Page 11 of33

---

Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: .L Event No.: Event

Description:

Turbine FirstStage Pressure Transmitter Failure Low Time I Position Examinee's Actions or Behavior i CRS/ATC Determine Channel A has NOT failed. CRS/ATC Check Steam Dumps NOT in Pn3ssure Place Steam Dumps in Pressure Place Steam Dump Controller in Manual (Panel *

• Adjust Steam Dump Controller output to 0% I

• Place Steam Dump Control Switch to RESET and return to PRESS CO NT

• Place Steam Dump Controller in AUTO I----' i CRS/BOP . Place BS/2MSS 400 block switch in AMSAC cabinet to BYPASS (UP) position to i block AMSAC system CRS Refer to Technical SpeCifications o TS 3.3.1-1 Function 17b Completion Time 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> o TS 3.3.1.1 Function 17e Completion Time 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> o TS 3.3.2-1 Function 19 AOT 6 Hours o TS 3.3.2-1 Function 4d AOT 6Hours o TS 3.3.2-1 Function 4e AOT 6Hours CRS/BOP Determine that NO redundant Bistable Status Lights are illuminated (Panel SOF) CRS/BOP Trip Bistables for PT -412B

• Rack White A-a Bistable LOOP 2B, High SF SI

• Rack White A-8 Bistabl'3 LOOP 4B, High SF SI

• Rack White A-9 Bistable LOOP 1 B, High SF SI

• Rack White A:9 Bistable LOOP 3B, High SF SI i CRS/BOP Check Bistable Status Light for failed instrument illuminated Lead Instruct the Booth to insert Event Tripping bistable has no impact on the remainder of the U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT -412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 12 of33 Appendix Scenario Outline Form Op-Test No.: _1_ Scenario No.: L Event No.: Event

Description:

RSC Leak/Small Break Time I Position Examinee's Actions or ATC Diagnose RCS

• Decreasing Pressurizer Level and Pressure (Panel FBF)

• PRZR LOW PRESSURE Annunciator

• PRZR LOW LEVEL Annunciator

• VC SUMP PUMP RUNNING Annunciator

• C.B. COOLER COND HIGH LEVEL Annunciator CRS Enter 1 CRS/ATC If At Any Time step to Isolate Leak if location is known. Determines location of leak is NOT i BOP I Determine plant is NOT on RHF! cooling If At Any Time Step to Trip the Reactor and Initiate SI if Pressurizer Pressure decreases to s 1930 psig. Evaluate RCS Pressure -If < 1930

• Trip the Reactor

• Verify Reactor Tripped

• Manually Actuate SI

• Go To E-O If At Any Time Step to Trip the Reactor and Initiate SI if Pressurizer Level cannot be maintained with 2 charging pumps in service and letdown flow at 45 gpm or < 14% Evaluate PRZR Level -If conditions are satisfied

• Trip the Reactor

• Verify Reactor Tripped

• Manually Actuate SI

• Go To E-O CRS/ATC As necessary:

BOP Increase Charging Pump Speed *

• Start 2 nd Charging i L

• Reduce Letdown to 45 I : CRS/ATC Determine there is NO PORV leakage. U3 NRC Scenario 3 Power increase from 35%,L T-460 fails low Restore Letdown; PORV 456 leak, PT 412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 13 of33 Appendix D Scenario Outline Form ES-D-1 CRS/ATC Determine there is NO indication of Valve Leakage CRS/ATC Determine leak is too large. Direct Reactor Trip and Safety Injection.

U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOeA. Page 14 of33 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: L Event No.: L Event

Description:

Reactor Trip and Safety Injection Time Examinee's Actions or Behavior When Unit trips. direct team to perform immediate actions of E-O

• Verifies immediate actions using the procedure. I When the CRS directs "Perform the Immediate Operator Actions of E-O, the A TC and BOP will first

• perform the IOAs silently only announcing unexpected conditions.

The crew will then re-perform the IOAs vfJrbalizim each item. Verifies Reactor Trip: (Panel FCF) Reactor trip and bypass breakers open Rod bottom lights lit IRPls < 20 steps i

• Nuclear flux decreasing ATC Verifies Turbine Trip by observing stop valves closed {Panel FAF} BOP Check status of 480V buses (Panel SHF)

• Observe ALL busses energized from Offsite Power Check SI Determine SI is Any SI Annunciator

-Lit (Panel FDF) SI Pum s An Runnm -* Panel SBF 1, SBF 2 ATC/BOP Manually Actuates SI if--"---+-----r----.

Depresses SI Actuation pushb'-u_tt_o_n...l.(_P_an_e".;...I_S_B_F-'-

_________-l1 Check AFW Status Observes Total of all SG flow indicators>

365 gpm (Panel SCF) Controls feed flow to maintain SG levels 9 -50% Ir--__-+____r---_.__A.;...d""'*..;.;.us"-'t'-.f...:.lo--'w control potentiometers CRS Direct BQP to perform RO-1 BOP Operator Actions durin use of EOPs U3 NRC Scenario 3 Power increase from 35%,L T-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 15 of33 Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.: L Event

Description:

Reactor Tri(:! and Safet;, Injection Time Examinee's Actions or Behavior ATe Verify Feedwater Isolation Check Main Boiler Feed Pumps Tripped (Panel FAF) Check MBFP Discharge Valves Closed (Panel FAF)

• Check Feed Reg Valves and Bypasses Closedllsolated 0 Main and Bypass MOVs Closed (Panel SCF) 0 Main FRVs 2 is True (Panel SNF) 0 FRVs (panel FAF} ATC Check Slowdown Isol(1tion Valves Closed (Panel ATC Verify SI

• Check Pressure < 1700 psig (panel FBF, or FDF) i

• Check High Head Pump Flow Indicators (Panel SBF-2)

• Check Pressure < 360 psig (Panel FDF WR Press Recorder)

ATC Verify Containment Spray NOT required

• Check Containment Pressure remained < 22

{Panel J01 or SBF-21 ATC Check RCP Seal Cooling !

• Bearing Coolant Low Flow Alarm Clear (Panel SGF) i

• Thermal Barrier CCW Header Low Flow alarm Clear (panel SGF) ATC Establish Charging Flow Check RCS Pressure>

360 psig (Panel FDF WR Recorder)

Check CCW Available (Panel SBF-1 lights only this is adequate; Panel SGF

• Breakers & Flow indicators) Check HCV 142 Fully Open (Panel SFF) Check CH-AOV-204B Open (Panel SFF) Open CH-LCV-112B (Panel SFF) Then Close CH-LCV-112C (Panels SFF) Set Speed Controller to Starting Position (Panel FBF) Start 1 Charging Pump (Panel FBF) Adjust Speed for Minimum Seal Injection (Panel SAF) U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 16 of33 I i Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: L Event

Description:

Reactor and Safety Injection Time Examinee's Actions or Behavior Check RCS Average Temperature

• Any RCPs Running -Tc,wg Trending to 547°F (Panel FDF)

• No RCPs running -Tcold Trending to 547°F (Panel FDF) If Temp < 547" and decreasing 0 Stop Dumping Steam 0 Control Total Feed Flow 0 Maintain>

365 until one SG > 9% 0 If cooldown continues, Close MSIVS If Temp> 547" and incn:!asing 0 Dump steam to condenser 0

Steam using Check if RCPs should be stoppEld

• At least 1 HHSI Pump running (Panel SBF-2)

• Subcooling

< value in table (QSPDS Monitor on i

• All Check PORVs Closed (Panel Check Safety Valves

• Tailpipe Temperatures Normal (Panel FBF)

• Acoustic Monitors Normal (Above Door into Supervisory Panel) : Spray Valves Closed (Panel Check Aux Spray Valve Closed Panel (Panel ATC Determine if SGs are !

• Any SG Pressure decreasing in uncontrolled manner (Panel FBF)

• Any SG depressurized

{Panel ATC Determine if SG Tubes are

• Condenser Air Ejector Radiation recorder Trend (Rad Monitor Rack)

• SG Blowdown Recorder Trend (Rad Monitor Rack)

• Main Steam Line Radiation Recorders (Rack 0-3 behind the Flight Panel)

• Any SG level in an uncontrolled manner (Panel FBF) U3 NRC Scenario 3 Power increase from 35%,LT -460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 17 of33 Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: L Event No.: L Event

Description:

Reactor Trip and Safety Injection Time i Position Examinee's Actions or Behavior ATC Check if RCS is intact

• Containment Pressure Normal (Panel J-O or SBF-1)

• Containment Sump Level Normal (Panel J-O)

• Containment Radiation Normal 0 R-2 and R-7(Rack D-1 Behind Flight Panel) I R-25 and R-26 CRS TO E-j Booth Operator : When crew enters E-1 Activate Trigger 7 l 0 U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-4l2B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 1.8 of33

.1 Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: 5 & 6

• Event

Description:

BOP Operator Actions -Automatic Action Verification I I Time Position Examinee's Actions or Behavior

---

'--------. . BOP Enter RO-1BOP Monitor Control Room

• Acknowledge Supervisory Alarms

• Report Unusual Alarms

• Monitor High Containment Temp alarm (SCF)

• Monitor 480 Safeguards Undervoltage alarm.>..

________--11 BOP Verify SI Pumps running

• Three SI Pumps (SBF-2)

• Two RHR Pumps (SBF-1 or BOP Verify Containment FCU

• Check all FCU running

• Place Damper Control Switches in Incident Mode (Panel SBF-2) o Damper AlB Closed o Damper C Closed o Damper D Open

• Place Control Switches for 1104 and 1105 to Open (Panel SBF-1)

• Check 1104 and 1105 BOP Verify SI Valve Alignment Proper Emergency

• Safeguards Valve Off Normal alarm CLEAR

• Ensure following OPEN o BIT Discharge 1835A1B (Panel SBF-2) o BIT Inlet 1852AJB (Panel SBF-2) o High Head Stop Valves 856J, H, C, E (Panel SBF-2)

• Check if MSIVS should remain OPEN o High Steam Flow SIIHi-Hi VC Pressure Alarm Clear (FDF)

• IF RWST Purification L()o in service contact NPO to secure. U3 NRC Scenario 3 Power increase from 35%,L T-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 19 of33 Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.:.....L Event No.: 5 & 6_ I* Event

Description:

BOP Operator Actions -Automatic Action Verification Time Examinee's Actions or Behavior BOP Verify Aux Boiler Feed Pump Status Check Motor Driven Pumps Both Running 0 Only 3'JAFW Pump is running Check Turbine Pump Running 0 Raise Speed of 32 AFW PUMP (Panel SCF) 0 OPEN Aux Feed Reg Valves 405A and 405B to feed 31 and 32 BOP Verify Aux Feed Valve Motor driven AFW Pumps (Panel SCF) 0 Set 406A -D to full open (Panel SCF)

• Check SG Blowdown isolation valves CLOSED (Panel SCF) BOP Check CCW Pumps

• All 3 Pumps Running i I I

• Check RHR HX CCW Shutoff Valves Open 822A1B (Panel SGF) I BOP Check Essential Service Water Pumps -3 Running BOP Verify Containment Ventilation Phase A & B (Panel SNF)

• Phase A actuated

• Phase B Actuated

• Check Phase A valve CLOSED ! I

• Check Phase B valves BOP Verify Containment Ventilation Purge Valves CLOSED 0 FCV-1170 -1173 (Panel SLF) Pressure Relief Valves CLOSED 0 PCV-1190 -1192 (Panel SLF)

• Check WCCPP Low Pressure Zone Alarms NOT Lit.

• Verify IVSWS Valves OPEN 0 I 0 U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 sa, Steam Generator Tube Rupture with LOCA. Page 20 of33

. Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: .l Event No.: 5 & 6_ Event BOP Actions -Automatic Action Time Position Examinee's Actions or BOP Verify Emergency Diesel Generator

• Check ALL EDGs RUNNING (Panel SBF-2)

• Check EDG Outlet Flow Control Valves OPEN 0 FCV-1176/1776A (Panel SBF-2} BOP Verify Control Room Ventilation Set Control Room Ventilation Control Switch to 10% incident mode (By Supervisory Panel Entrance) Check Damper Status 0 A-Dim 0 B -Bright0 Either F1 or F2 0 Dampers D1 and D2 Bright Verify AlC Compressors and fans ALL Running 0 ACC 31A1B ON Bright 0 ACC 32 AlB 01\1 Bright 0 ACF 31/32 ON Bright Verify Emergency DC Oil Pump Status

• Main Turbine Emergency Bearing Oil Pump Running (Panel SEF) i

• Dispatch NPO to verify Main Gen Air Side Seal Oil Pump Running

• MBFP DC Em§lrgency Oil Running (Alarm Panel SDF) i BOP Reset Safety Injection Press both SI Reset buttons (Panel SBF-2) Check SI Reset 0 SI Actuated light BOP Reset If RCS pressure is < 360 psig place Makeup Control Switch to stop Dispatch NPO to secun::! VC Sump and RCDT Pumps on Waste Disposal Panel

• Dispatch NPO to align and reset MCC per SOP-EL-15 U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 21 of33 i Appendix Scenario Outline Form ES-O-1

• Op-Test No.: Scenario No.: ..l.. Event No.: 5 & 6 Event

Description:

BOP Operator Actions -Automatic Action Verification Time Examinee's Actions or Behavior BOP Check if additional actions should be performed If transition to ES-1.1 0 Inform CRS of Automatic Action Verification 0 Do not perform additional steps

• If Not transition to ES-1.1 0 Inform CRS of Automatic Action Verification I 0 When transition out of E-O then continue U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 22 of33 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: L i . Event

Description:

Small Break LOCA . Time I Position Examinee's Actions or Behavior i I CRS Enter ATC Check if RCPs should be

• At least 1 HHSI Pump running (Panel SBF-2)

• Subcooling

< value in table (QSPDS Monitor on desk)

All ATC Determine if SGs are

• Any SG Pressure decreasing in uncontrolled manner (Panel FBF)

• Any SG Completely depressurized (Panel ! Determines NO SG ATC/BOP Check Intact SG

• Check Level Response in all SGs Normal (Panel FBF)

• Control Feed Flow to maintain 9 [141-50% It is possible that the crew ma)' diagnose the SGTR at this point and may transition to E-3 ATC/BOP Reset SI

• Check RO-1 Steps 2 -complete (report from BOP) Press both SI Reset Push buttons (Panel SBF-2) *

• Check SI Reset 0 SI Actuated Light Extinguished (Panel ATC/BOP Reset Phase A and

• Place switches for 200 A, B, C in Close (Panel SFF)

• Depress Phase A Reset pushbuttons (Panel SNF)

• Depress Phase B Reset push buttons If Actuated (Panel SNF) .. .. U3 NRC Scenario 3 Power increase from 35%,L T-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

3 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 23 of33 Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.: Event

Description:

Small Break LOCA Time Position Examinee's Actions or Behavior CRS Check Secondary Radiation ATC/BOP

• Check Seismic Event NOT occurred (Alarm on SDF Clear)

• Direct Watch Chemist to Sample SGs

• Direct Watch HP to perform contact surveys steam lines & blowdown lines Reset SG Sample 0 Place Blowdown Switches to Close 0 Press SG Blowdown & Sample Valves Reset Push buttons 17 -24 on Panel SMF Check secondary radiation 0 R-15 (Radiation Monitor Control Cabinet 0 R-19 (Radiation Monitor Control Cabinet 0 R-62 A-D (Rack D3 Behind Flight Panel)

• Check level in isolated SGs Stable (Panel FBF) It is expected that the crew diagnose the SGTR at this pOint and may transition to E-3. "the crew continues in E-1, they will be required to transition to E-3 on foldout page criteria.

ATC Check PRZR PORVs and Block Valve Check Power Available to Block Valves 0 Check Breakers for MCC-36A1B closed (Panel SBF-2) 0 Check Block Valves both energized (Panel FBF)

• Check PORVs Closed (Panel FCF)

• Open one Block Valves_Wanel BOP/ATC Establish Instrument Air to

• Check Inst. Air Low Press Alarm Clear (Panel SJF)

• Press Inst. Air Reset Pushbutton 28 (Panel SMF)

• Open IA-PCV-1228 (Panel SNF) I 0 IA-PCV-1228 will NOT OPEN U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 24 of33 Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.:L Event

Description:

Small Break LOCA Time Position Examinee's Actions or Behavior ATC/BOP Check RCP Seal Cooling

• Seal Injection Established (Panel SAF)

OR

• Bearing Coolant Low Flow Alarm Clear (Panel SGF)

• Thermal Barrier CCW Header Low Flow alarm Clear (Panel SGF) ATC/BOP Check CCW for Charging Pump Available

• Check Pumps operating (Panels SBF-1 or ATC Determine jf Charging Flow Has Been

• Check LCV-112B and LCV-112C both energized and one open (Panel SFF)

• Check CH-AOV-204B Open (Panel SFF)

• Check HCV-142 Fully Open (Panel SF F)

• Check/Start a Charging Pump (Panel FBF) CRS ATC Check if SI should be

• Subcooling

> 40°F [Table for Adverse] (QSPDS Monitor on Desk)

• Secondary Heat Sink o Total Feed Flow> 365 gpm Available (Panels SCF) o SG Level> 9% [14%] (Panel FBF)

• RCS Pressure o > 1700 psig [2000] (Panel FDF) o Stable or Increasing

• Pressurizer Level> 14% [32%] (Panel FBF) 51 Termination Criteria will NOT be met U3 NRC Scenario 3 Power increase from 35%,LT -460 fails low Restore Letdown; PORV 456 leak, PT -412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 25 of33 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: Event Steam Generator Tube R re with Small Break LOCA Examinee's Actions or Behavior , Check if RCPs should be stopped

• At least 1 HHSI Pump running (Panel SBF-2)

• Subcooli < value in table PDS Monitor ATC Identify Ruptured Unexpected Levellncre,ase 32 SG (Panels FBF or SCF) High radiation from any SG Sample (Chemistry Report) High radiation from any Steam Line (Rad Monitor Control Cabinet, QSPDS, D-Racks behind ht Panel ATC Isolate Flow From Ruptured 32 SG Adjust Atmospheric to 1040 and check closed (Panel FBF) 32 is affected -direct NPO to isolate steam to 32 AFW Pump Trip 32 AFW pump if at least 1 MDAFW pump running (Panel SCF) SG-33 Close MS-42 Restart 32 AFW Pump if necessary (Panel SCF) Verify Blowdown Isolated (Panel SCF) Dispatch NPO to isolatet Upstream steam traps per Operator Aid Close 32 SG MSIV (Panel SBF-1) Check Rupture SG Level> 9% [14%]

• Stop Feed Flow to ruptured SG (Panel SCF) This action ATC/BOP Check Ruptured SG pressure>

400 psig (Panel FBF)

• Transition to ECA-3.1 if < 400 . This is U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 26 of33 Appendix Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: -.L Event No.: Event

Description:

Steam Generator Tube Rupture with Small Break LOCA Time Examinee's Actions or Behavior CRS/ATC Determine Target Temperature for Determine Pressure of Huptured SG (Panel

• Using Table Determine Target Temperature Dump Steam to condenser from intact SGs do not exceed 0.4 E6 Ibm/hr per intact SG.j ATC Procedure actions continue until coo/down termination criteria are met. ATC Stop cooldown when CET temp (QSPDS) is less than target i Close Steam Dumps/Atmospherics (Panel FCF/FBF) 0 Null deviation meter on controller to match Auto setpoint with actual current pressure.

0 Close valves in manual 0 Place controller in automatic ATC Maintain CET temp < target temp Monitor CET Temperature and adjust controller setpoint to control < target temp ATC/BOP Check Intact SG Levels

• Level response Normal (Panel FBF and/or SCF)

• Control feed flow to maintain level 13% [19%] to 50% (Panel SCF) ATC Check PORVs and Block Valves Check power available to block valves (lights lit) (Panel FCF) Check PORV Closed 0 Light indicating PORVs closed (P':lnel FCF) 0 Tailpipe Temperatures consistent with plant conditions (Panel FBF) 0 Accoustic Monitors No lights lit. (Above door into Supervisory Panel) Check Block Valves Open 0 Both Block Valves are CLOSED to isolate leaking PORVs. i 0 The Block Valves should be left shut U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 27 of33 II Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: --L Event No.: L-Event

Description:

Steam Generatqr Tube with Small Break Time I Position Examinee's Actions or ATC/BOP Reset

• Check RO-1 Steps 2 -12 complete (report from BOP)

• Press both SI Reset Push buttons (Panel SBF-2) Check SI Reset 0 SI Actuated Light Extinguished (Panel SBF-2) -ATC/BOP Reset Phase A and B

• Place switches for 200 A, B, C in Close (Panel SF F)

• Depress Phase A Reset pushbuttons (Panel SNF)

• Phase B Reset

{panel SNF) BOP/ATC Establish Instrument Air to Containment

• Check Inst. Air Low Press Alarm Clear (Panel SJF)

• Press Inst. Air Reset Pushbutton 28 (Panel SMF)

• Open IA-PCV-1228 (Panel SNF) 0 IA-PCV-1228 will NOT BOP ! Determine if RHR Pumps should be

• Check RCS Pressure>

360 psig [700] (Panel FDF or SFF) I

• RHR and in Auto (Panel SGF)

ATC/BOP Check RCP Seal Cooling

• Seal Injection Established (Panel SAF) OR

• Bearing Coolant Low Flow Alarm Clear (Panel SGF) * ... Thermal Barrier CCW Header Low Flow alarm Clear (Panel SGF) U3 NRC Scenario 3 Power increase from 35%,LT -460 fails low Restore Letdown; PORV 456 leak, PT -412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 28 of33 Appendix Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: EventNo*:L Event

Description:

Steam Generator Tube Rupture with Small Break LOCA Time Examinee's Actions or Behavior Establish Charging Flow Check CCW for Charging Pump Available 0 Check Pumps operating (Panels SBF-1 or SGF)

• Check HCV-142 Fully Open (Panel SFF)

• Check CH-AOV-204B Open (Panel SFF)

• Open LCV-112B then close LCV-112C (Panel SFF)

• Check/Start a Charging Pump and adjust to maximum (Panel FBF) Expect a charging pump is already running at this point. Actions to terminate coo/down repeated be/ow. If crew get to this step before they should wait here. When CET Temps, target temp then they should Check if cooldown should be stopped --CET temp (QSPDS) is less than target temp. Close Steam Dumps/Atmospherics (Panel FCF/FBF) 0 Null deviation meter on controller to match Auto setpoint with actual current pressure.

0 Close valves in manual 0 Place controller in automatic to maintain temp ATC Check SG Pressure Stable or (Panel FBF) ATB/BOP Check subcooling based on CETs > 60°F [see table for adverse values] Depending on value for subco,oling, the crew should transition to ECA-3.1 at this point Depressurize RCS using PRZR Spray flow

• Spray flow is NOT ATC Depressurize RCS Using PRZR Check PORVs available 0 PORVs indicating lights lit 0 PORV Block Valve Energized/Open

• Open one PORV

• Check Pressure Decreasing (Panel FBF) U3 NRC Scenario 3 Power increase from 35%,L T -460 fails low Restore Letdown; PORV 456 leak, PT -412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LoeA. Page 29 of33 Appendix Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: Event No.: L Event

Description:

Steam Generator Tube Rupture with Small Break LOCA Time Position Examinee's Actions or Behavior ATC Terminate Depressurization whe:n: Both oRCS Pressure < Ruptured SG Pressure (Panel FBF) o PRZR level> 14% [50] (Panel FBF) OR

• PRZR Level> 73% [58] (Panel FBF)

• Subcooling

< 40° [See Table for Adverse] A TC Stop

• Close PORV (Panel ATC Check RCS Pressure Increasing (Panel CRS ATC Check if SI should be BOP

• Subcooling

> 40°F [Table for Adverse] (QSPDS Monitor on Desk)

• Secondary Heat Sink o Total Feed Flow> 365 gpm Available (Panels SCF) o SG Level> 9% [14%] (Panel FBF)

• RCS Pressure o Stable or Increasing

• Pressurizer Level> 14% [32%] (Panel FBF) If not accomplished prior to this step, the crew should transition to ECA*3.1 at this time. U3 NRC Scenario 3 Power increase from 35%,L T-460 fails low Restore Letdown; PORV 456 leak, PT-4128 failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 30 of33 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: -Event No.: Event

Description:

Time Position Examinee's Actions or CRS Enter ATCIBOP Reset

• Check RO-1 Steps 2 -12 complete (report from BOP)

• Press both SI Reset Push buttons (Panel SBF-2)

• Check SI i 0 SI Actuated Light Extinguished (Panel Reset Phase A and Place switches for 200 A, B, C in Close (Panel SF *

• Depress Phase A Reset pushbuttons (Panel SNF)

• Depress Phase B Reset push buttons If Actuated (Panel SNF} BOP Establish Instrument Air to Containment

• Check Inst. Air Low Press Alarm Clear (Panel SJF)

• Press Inst. Air Reset Pushbutton 28 (Panel SMF)

• Open IA-PCV-1228 (Panel SNF) I 0 IA-PCV-1228 will NOT i .. --.. BOP Check Status of 480V All energized byu off site Ensure MCC and lighting are reset per I CRS/ATC I Align PRZR Heater

• Control Group Trip Pull Out I !

• Backup Groups I I CRSATC . Check if Spray Pumps should be Containment spray wj3s never activated

• CRS/ATC Check 32 SG Level > i

• Stop Feed Flow to 32 SG I CRS/BOP I Determine if RHR Pumps should be stopped i RHR Pumps were previously st()eeed U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 31 of33 Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.: Event Ilo,et"'r'l"Itlrln' Time Examinee's Actions or CRS/BOP Evaluate Plant Status usi Attachment CRS/ATC Check Seal Cooling Seal Coo CRS/ATC Establish Charging

• Charging Flow Previously Established using one pump

• Start all available charging pumps

• Establish Maximum Flow CRS/ATC Determine SGs are NOT Faulted CRS/ATC Check Intact SG Level NORMAL CRS/ATC Initiate RCS Cooldown to Cold Shutdown

• Verify All control rods < 20 steps

• Maintain Cooldown Rate < 100 0 Ihour CRS/ATC Determine if Subcooled Recovery is appropriate

• RWST Level> 24 Feet

• 32 SG NR levels < d Examiner Terminate U3 NRC Scenario 3 Power increase from 35%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 32 of33 Appendix 0 Scenario, Outline Form ES-D-1 Post Scenario Event Classification Event Classification

-ALERT EAL 3.1.2 Primary system leakage exceeding the capacity (>75 gpm) of a single charging pump. U3 NRC Scenario 3 Power increase from 35%,L T-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA);

31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA. Page 33 of33 Appendix Scenario Outline Form ES-D-1 Facility:

IPEG Unit 3 Scenario No . Op*Test No.: 1 Operators:

Initial Conditions:

100% power steady state. 32 HHSI pump is OOS, expected to return to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Turnover:

Maintain 100% Power Event Malf. Event Event No. No. Type* Description MAL* I (CRS) PT-404 failure requiring manual control of Main Boiler Feed Pumps. MSS003 I (ATC) MAL-C (ALL) Fault on 480V Bus 6A. This will require starting an ESW pump and EPS005 charging pump. TS D (CRS) 3 N/A R (ATe) T.S. load reduction.

N (CRS) N (BOP) 4 MAL-C(ALL) Rod K-14 fails to move during power reduction CRF004 TS AU (CRS) MAL-i M (ALL) SBLOCA RCSOO1 A 6 C (ALL) ATWS RPSOO2 AlB 7 C (BOP No Auto SI SIS001A IB , , C (CRS) . II * {N)ormal,

{Qnstrument, {C)omponent, (M)ajor U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page I of35 Appendix Scenario Outline Form ES-D-1 Summary The evaluation begins with the plant at 100% power steady state operation.

32 SI pump is out of service for bearing inspection.

32 SI Pump was removed from service 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago, expected return in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. After the crew assumes the watch, PT-404 Steam Header Pressure fails high. ATC diagnoses failure and places Main Boiler Feed Pump speed control to manual. CRS directs crew to perform AOP-INST-1, Instrument/Controller Failures.

Next, a fault occurs on Bus 6A. Team enters AOP-480V-1, Loss of 480 V Bus to stabilize the plant. The crew will start a charging pump, ESW Pump and determine that a shutdown must commence.

This is a Tech Spec for the CRS. During shutdown Control Bank D rod K-14 fails to move. The crew will respond using AOP-ROD-1.

Reactor Engineering will direct the crew to continue with the shutdown allowing rods to step in. This is a Tech Spec for the CRS. After sufficient shutdown, a SBLOCA occurs. Auto reactor trip is demanded but the Reactor trip breakers do not open. The reactor will not trip from the Control Room and the team will respond per FR-S.1, "Response to Nuclear Power Generation I A TWS" and will SID the reactor by manually inserting control rods and initiating Emergency Boration via an alternate method since MOV-333 cannot be opened from the Control Room. The turbine will be manually tripped. The reactor trip breakers will be locally opened and the team will transition to E-O, "Reactor Trip or Safety Injection".

An Auto SI is required, but will not actuate. The RO will manually actuate SI. 33 SI pump cannot be powered. 32 SI pump is OOS. 31 SI pump initially starts but trips. 31 and 32 Charging Pumps are eventually started after manual action to align suction to the RWST. The team will diagnose RCS not intact and transition to EOP E-1, Loss of Reactor or Secondary Coolant. As the team progresses through E-1, Reactor Vessel level will continue to lower. When level lowers to 44% RCP running range (after about 30 minutes following the ATWS), an orange path on core cooling will require a transition to FR-C.2, Response to Degraded Core Cooling. The team will initiate depressurization of SGs per FR-C.2. The scenario is terminated after SG depressurization has Deen initiated.

Procedure Flowpath:

AOP-INST-1, AOP-480V-1, AOP-ROD-1, FR-S.1, EOP E-o, EOP E-1, FR-C.2 Critical Tasks are as follows: FR-S.1 -Insert negative reactivity into the core by at least one of the following methods before step 4 of FR-S.1 is complete:

o De-energize the Rod Drive MG Sets o Manually insert the rods o Establish Emergency Baration FR-S.1 --Start AFW pumps and establish 686 gpm before transition out of FR-S.1 E-o --Manually actuate at least one train of SIS actuated safeguards before completion of S.1 step 6 FR-C.2 Depressurize SGs to atmospheric pressure (at < 100°Flhr) to inject ECCS accumulators and establish low-head injection flow before a Core Cooling red path develops.

U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 2 of35 Appendix Scenario Outline Form ES-D-1 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS IEXPECTED RESPONSE/INSTRUCTOR CUES IC Reset Simulator to IC-11 SES Setup Insert override SWI-SIS002G to PULL OUT POS Sf PUMP #32 CONT On Insert malfunction MAL-SIS004A SAFETY INJECTION PUMP 31 FAILURES to TRIP Insert malfunction MAL-REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO RPS002A to ALL_FAIL FAILURE) Insert malfunction MAL-REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO RPS002B & MANUAL) Insert malfunction MAL-SIS001A SAFETY INJECTION FAILURE TRAIN A Insert malfunction MAL-SISOO'I B SAFETY INJECTION FAILURE TRAIN B Insert malfunction MAL-MSS003 STEAM HEADER PRESSURE DETECTOR PT-404 to 1200.00000 in 40 on event 1 FAILURE nsert malfunction MAL-LOSS OF 480 V BUS 6A EPS005D on event 2 Insert malfunction MAL-Res RUPTURE (LOOP I COLD LEG) RCS001A to 0.50000 on event 5 Insert malfunction MAL-STUCK ROD (CBD-KI4)

CRF004AU to UNTRIPPABLE Local Reactor Trip Removes Malfunctions:

Delete malfunction MAL-REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO RPS002A to ALL FAIL FAILURE) Delete malfunction MAL-REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO RPS002B & MANUAL) Insert remote LOA*CVC034 to 288 RWST TO CHARGING PUMP HEADER ISO 1.00000 Insert remote LOA-SIS014 to NONE LOA TO DEENERGIZE VALVE 894A ENERGIZE in 360 Insert remote LOA-SIS015 to NONE LOA TO DEENERGIZE VALVE 894B ENERGIZE in 360 Insert remote LOA*SIS016 to NONE LOA TO DEENERGIZE VALVE 894C ENERGIZE in 360 Insert remote LOA-SIS017 to NONE LOA TO DEENERGIZE VALVE 894D ENERGIZE in 360 Set RCCH822B=1 in 600 Locally open 822B SES Setup Load Schedule and verify ! Schedule malfunctions and overrides bave been entered Floor Setup Perform Setup Checklist Hang Danger Tags on 32 HHSI Pump Update Protected Equipment Hang Protected Equipment Tags for 31 and 33 PC HHSI Pumps Risk is ????? Event Activate Trigger 1 when MAL-MSS003 PT-404 failure directed U3 NRC Scenario 4. PT*404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 3 of35 I Appendix 0 Scenario Outline Form ES-D-1 Role Play Respond as requested Event 2 Activate Trigger 2 when directed Role Play Respond as requested Event 3 No action

• Role Play

• Respond as requested i Event 4 Inserted at setup Role Play

• Respond as requested Event 5 I Activate Trigger 5 when

• directed Role Play Respond as requested I Event 6 Inserted at setup Role Play I When NPO directed to locally trip reactor Event 7 ! Inserted at Setup I I Role Play il Respond as requested NPO may be directed to investigate PT -404 and MBFP I&C will prepare a Troubleshoot and Repair Package

• MAL-EPS005D Fault on bus 6A

• Report acrid smell in 480V switchgear room when asked to TS 3.0.3

• If necessary SM direct initiate shutdown

• immediately MAL-CRF004AU Rod K-14 stuck I&C will prepare a Trouble Shoot and Repair Package I MAL-RCS001A RCS Leak i I MAL-RPS002A (Trip breakers fail to auto open) MAL-RPS002B (Trip Breakers fail to man open) ATWS After emergency boration initiated, REMOVE MAL-RPS002A and MAL-RPS002B MAL-SIS001A Auto Failure Train A Sl MAL-SIS001 B Auto Failure Train B SI U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank 0 rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 4 of35 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: _1_ Event

Description:

PT-404 Failure High -Manual con1trol of Main Boiler Feed Pumps Time Position Examinee's Actions or Behavior ATC/BOP Diagnose Failure of PT-404 ATC Place both MBFPs in Manual and stabilize plant. CRS Direct Perform Immediate Operator Actions of AOP-INST-1 ATC Silently evaluates for failure of control system inputs

• Rod Control o NIS Power Range oRCS Temp o Turbine 1 51 Pressure

• Pressurizer Pressure Pressurizer Level Control oRCS Temperature

• MBFP Speed Control o Suction Pressure o Discharge Pressure o Steam Header Pressure

• SG Level Control o Steam Pressure o Steam Flow o Feedwater Flow

• SG Pressure Control o Atmospheric Steam Dumps o High Pressure Steam Dumps CRS/ATC Enter AOP-INST-1 and Re-perform IOAs verbaliz.ing each input CRS/ATC Determine an Instrument failure has occurred.

U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR.-C.2 Page 5 of35 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: _1_ ! Event

Description:

PT -404 Failure High -Manual control of Main Boiler Feed Time Position Examinee's Actions or CRS Identify appropriate section 4.17 of

• Determine Steam Dumps are in Temperature Mode -No action required. (Panel FBF) ATC Determines Main Boiler Feed Pumps are in Manual (Panel FAF) This should have been done as part of the Immediate Operator Actions ATC Adjust MBFP Speed to Match Steam Flow and Feed Flow. When stable, adjust Feed Reg Valve AP Program 13 Return controls for unaffected equipment to auto as desired. The FRVs may have ! been placed in manual, they can be returned to auto here. I ! Lead Evaluator Instruct Booth to insert Trigger 2 I! U3 NRC Scenario 4. PT -404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 6 of35 I Appendix Scenario Outline Form ES-D-1 S",c"QiIU Event

Description:

Loss of 480V Bus 6A Time Examinee's Actions or Behavior CRS/BOP Multiple alarms -Diagnose Loss of Bus CRS Enter

• CRS/BOP Determine power is lost to Bus 6A and RHR was not in service CRS/ATC Determine no Charging Pump is running

• Start 31 or 32 Charging Pump and match speed with previous conditions CRS/BOP Determine 2 CCW Pumps are running Determine Essential Service Water Header Pressure is < 60 psig and no SW pumps are operating on the Essential SW Header

• Start 34 or 35 SW CRS/ATC Determine Turbine is on CRS/ATC Determine Power has not been lost to IRPI CRS/ATC Determine Vacuum NOT decreasing BOP CRS/BOP Determine ISO PHASE BUS RETURN AIR HIGH TEMP alarm is clear CRS/BOP Determine waste release is NOT in BOP Dispatch operator to monitor CRS/ATC Determine IRPI is CRS Initiate Review of Tech

• TS 3.8.9 E -Inoperable train with loss of safety function

• TS 3.5.2 -2 Inoperable HHSI Pumps (Loss of safety function)

U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 7 of3S Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.: Event

Description:

Loss of 480V Bus 6A Time I Position Examinee's Actions or

! Determine that 2 SIS pumps are inoperable necessitating a shutdown per T.S. I CRS 3.8.9 E ! . CRS/BOP Determine bus 6A NOT energized by EDG !CRS/BOP Determine 32 EDG is running ! BOPINPO Determine white supervisory light for relay 86/6A is extinguished BOP/NPO Dispatch an operator to: OPEN Breakers for 0 MCC-36B 0 MCC-36D 0 MCC-37

• Perform visual inspection of 480V bus 6A ! The NPO will report NO FIRE; however an acrid smell exists in the 480 V switchgear room and bus 6A is damaged. CRS/BOP Place Control Switches/breakers for 480V loads in pullouUoff/open 0 33 Charging Pump 0 PRZR Modulating Heaters 0 32 Boric Acid Transfer Pump 0 32 Containment Spray l:Jump 0 32 Recirc Pump 0 MCC36B 0 33 SI Pump 0 35 FCU 0 33 ABFP 0 Turb Aux Oil Pump 0 32 RHR Pump 0 33 SW Pump 0 36 SW Pmp I 0 39 SW Pump U3 NRC Scenano 4. PT-404 Failure HIgh Manual control MFW Pumps; Fault on Bus 6A; TS requIred shutdown; During Shutdown I Control Bank 0 rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip sllccessful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 8 of35 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: .L

• Event Loss of 480V Bus 6A Time I Position Examinee's Actions or Behavior I CRS Determine indication of Fault on Bus i i BOP Direct operator to shutdown 32 U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank 0 rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 9 of35 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: Event

Description:

Power Reduction Time Position I Applicant's Actions or Behavior Note: The reactivity plan for the power reduction should be developed by the team in the briefing room prior to takin ;J the watch. The plan could call for boration and/or rod insertion

,...CRS . ....."'P-2.1 and SM for Qower reduction CRS Use Attachment 3 from POP-2.1 for power reduction CRS Record power reduction data and contact the SM to make required notifications CRS Direct A TC/BOP to perform a Reactivity Calculation for the power reduction ATC/BO..... i'i<;;fJare Reactivity Calculation using the Daily Reactivity Sheet, OP CRS Assigns roles for power reduction ATC Reviews reactivity plan ATC If rods are inserted:

• Places/verifies rods are in Manual

• Inserts rods specified number of steps Observes:

0 Proper rod motion 0 Tavg 0 Power BOP Peer checks rod insertion ATC Diagnose Rod K-14 Not inserting with the remainder of Control Bank D NOTE: If the crewe/ec:ts to use boration first, there will be some time before rod motion is rE!Cluired.

CRS Suspend Power Reduction Enter AOP-ROD-1 U3 NRC Scenario 4. PT*404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaJigned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 10 of35 Appendix Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: Event No.: Event

Description:

Power Reduction Position ATC BOP ATC/BOP ATC ATC Lead Evaluator Applicant's Actions or Behavior If boration is performed: Energize All Pressurizer Heaters Places RCS Makeup control to Stop Place RCS Makeup Mode selector to borate Adjusts integrator to desired boration Places RCS Makeup control to

• 0 Proper makeup 0 0 Peer check boration Initiate Turbine Load Reduction at desired rate Governor (Preferred) Load Limit 1

• Load Limit 2 Maintain the manual setpoint for the MFRV Controllers Nulled. Adjust Control Rod Position per TS and Graph-RPC-16 When the following has been demonstrated/observed: Sufficient load reduction.

• Sufficient normal plant operations by the BOP. Then instruct Booth to insert Event. U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sl Fails; Loss ofal! Sf Pumps results in FR-C.2 Page II of35 Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.:....1...

Event No.: Event

Description:

Power Reduction/Stuck Rod K-14 Time I Position Examinee's Actions or Behavior I . i CRS I Enter AOP-ROD-1

!

• I CRS/ATC

• Determine procedure was NOT entered due to continuous rod motion

• CRS Determine procedure section 4.42 for misaligned rod CRS/ATC Determine rod is misaligned I A TC If not already accomplished for power reduction, place rod control in Manual *

• If At Any Time step for power reduction a Adjust boron concentration and turbine load Refer to Tech Specs a TS 3.1.4 Group Alignment Limits a TS 3.2.3 Axial Flux Difference o TS 3.2.4 Quadrant Power Tilt Depending on how quickly the crew diagnoses the stuck rod, actual Tech Spec limits may not be exceeded.

The OPERABILITY of rod K-14 is in Ir-____-+_________

BOP Notify I&C to investigate rod control system for the cause of misaligned/stuck rod. i ;r--_________--I--'R'-'-eport as I&C there is NO obvious cause for the misaligned rod. Lead When sufficient load reduction and progress throL1gh AOP-ROD-1 direct booth to activate event 5 U3 NRC Scenario 4. PT -404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 12 of35 Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: Event No.: l Event

Description:

SBLOCA I Time Position Examinee's Actions or Behavior i ATC Diagnose decreasing Pressurize Pressure and Level. CRS Direct ACT to trip the reactor ancl when verified tripped, Ii Direct the BOP to initiate Injection ATC Verifies Reactor NOT Tripped: (Panel FCF)

• Reactor trip and bypass breakers NOT open

• Rod bottom lights NOT lit

• IRPls NOT < 20 steps I * .. Nuclear flux NOT decreaslDg BOP

• to Tril2 the reactor using the l2ushbutton on Panel SBF-2 i BOP I Direct NPO to locally tril2 the reactor in the cable spreading room i CRS/ATC Determine power is > 5% and transition to U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 13 of35 Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.:..ft...

Event Descri A TWSI FR-S.1 Time Position Examinee's Actions or Behavior CRS Enter FR-S.1-Direct crew to ",c,,'rr'lrlrTl Immediate l"'t:>,r<>t."r Actions of FR-S. 1 CRS/ATC Determine reactor NOT tripped ATC

• May take manual control and insert rods

• let automatic control insert control ATC Determine Turbine NOT

• Manually trip Turbine BOP Check Auxiliary Feedwater Pumps Running NONE running

• Start 31 AFW Pump

• Start 32 AFW Pump o Increase speed and open throttle valves to feed 33 & 34 SG U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown J Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 14 of35 Appendix 0 Scenario Outline Op-Test No.: _1_ Scenario No.: Event No.: Event Descri on: ATWSI FR-S.1 Time Position Examinee's Actions or Behavior ATC Initiate Emergency Boration

• Check 31/32 charging pump running

• Determine MOV-333 cannot be opened. o Place FCV-110A in Manual o Ensure FCV-110A Fully Open (Controller output = 0) o Place 111A in Manual o Ensure 111A is Fully Closed (Controller output =0) o Place Makeup Mode Selector Switch in MANUAL o Turn Makeup Control Switch to START o Transfer Charging Pump to Manual o Increase Charging Pump Speed to maximum o Close Boric Acid Storage Tank Recire Valves BOP Verify Containment Ventilation Isolation

• Purge Valves CLOSED o FCV-1170 -1173 (Panel SLF)

• Pressure Relief Valves CLOSED o PCV-1190 -1192 (Panel SLF)

• Check WCCPP Low PrE!SSUre Zone Alarms NOT BOP Check SI

• Determine SI Not Actuated o Manually actuate SI o Perform E-O 35 -42 in with this ure U3 NRC Scenario 4. PT-404 Failure High -Manual control. MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip successful; Auto Sl Fails; Loss of all SI Pumps results in FR-C.2 Page 15 of35 Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: ATC Check Reactor Subcritical

• Power Range < 5%

• Intermediate Range Channels 0 or negative

• Check all rods < 20 steps Manual actuation of SI in previous step will strip the Rod Drive MG sets r .."'U'TI,nn in a reactor Booth Instructor Remove malfunctions for Reactor Trip Breakers and ensure reactor trip occurs. Remove MAL-RPS002A

&

CRS/ATC Secure Emergency BOP

• Turn Makeup Control Swi:tch to

• Establish Auto Makeup per SOP-CVCS-003

• Place Boric Acid Transfer Pumps in Slow Speed

• BAST Recirc control to CRS/ATC Check RCP Seal Coo Ii CRS/BOP Check Charging

• Check CCW available for Charging pump

• Check Charging Pump Running

• Maintain seal 'ection 6 -CRS/ATC Verify Adequate Shutdown BOP

• Verify Control Rods < 20

• Direct Chemist to Sample RCS

• Check Boron> Cold Shutdown Concentration o Establish normal U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 16 of35 Appendix Scenario Outline Form Op-Test No.: _1_ Scenario No.: Event No.: l Event SBLOCA I Position I Examinee's Actions or Behavior , CRS i Return to E-O ATC Verifies Reactor Tripped: (Panel

• Reactor trip and bypass breakers open

• Rod bottom lights lit

• IRPls < 20 steps _.

• Nuclear flux decreasing I I ATC Verifies Turbine Trie observing stoe valves closed {Panel FAF} BOP Check status of 480V buses (Panel SHF) Observe ALL busses energized from Offsite Power Check SI Determine SI is

• Any SI Annunciator

-Lit {panel FDF)

• SI Running (Panel SBF-1, SBF-2) ATCIBOP Manually Actuates SI Actuation pushbutton

{panel Check AFW Status Observes Total of all SG flow indicators>

365 gpm (Panel SCF) Controls feed flow to maintain SG levels 9 -50% t. Adjust flow control valve potentiometers. . !CRS i Direct BOP to RO-1 BOI? Operator Actions during use of EOPs ATC Verify Feedwater Isolation

• Check Main Boiler Feed Pumps Tripped (Panel FAF)

• Check MBFP Discharge Valves Closed (Panel FAF) Check Feed Reg Valves and Bypasses Closedllsolated 0 Main and Bypass MOVs Closed (Panel SCF) 0 Main FRVs 2 is True (Panel SNF) 0 Bypass FRVs (Panel FAFL___.___. I ATC Check Blowdown Isolation Valves Closed (panel SCF) U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 17 of35 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: l Event

Description:

SBLOCA Time Examinee's Actions or Behavior ATC Verify SI Flow Check Pressure < 1700 psig (Panel FBF, or FDF) Check High Head Pump Flow Indicators (Panel SBF-2) Check Pressure < 360 p!;ig (Panel FDF WR Press Recorder)

• Check RHR Pumps Flow Indicators (Panel ATC Verify Containment Spray NOT

• Check Containment Pressure remained < 22 I2si9 (panel J01 or SBF-2} ATC Check RCP Seal Cooling

• Bearing Coolant Low Flow Alarm Clear (P::mel SGF)

• Thermal Barrier CCW Header Low Flow alarm Clear (Panel SGF) ATC Establish Charging Flow Check RCS Pressure>

360 psig (Panel FDF WR Recorder) Check CCW Available (Panel SBF-1 lights only this is adequate; Panel SGF Breakers & Flow indicators) Check HCV 142 Fully Open (Panel SFF) Check CH-AOV-204B Open (Panel SFF) Open CH-LCV-112B (Panel SFF) Then Close CH-LCV-112C (Panels SF F) Set Speed Controller to Starting Position (Panel FBF) Start 1 Charging Pump (Panel FBF)

• Adiust Speed for Minimum Seal Injection

{Panel ATC Check RCS Average Any RCPs Running -Tavg Trending to 547°F (Panel FDF)

• No RCPs running -Tcold Trending to 54rF (Panel FDF) ATC Check if RCPs should be stopped At least 1 HHSI Pump running (Panel SBF-2) Subcooling

< value in table (QSPDS Monitor on desk) Stop All RCPs U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 18 of35 I Appendix Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: Event No.: l Event

Description:

§BLOCA Time Examinee's Actions or Behavior Check PORVs Closed (Panel Check Safety Valves

• Tailpipe Temperatures Normal (Panel FBF)

• Acoustic Monitors Normal (Above Door into Supervisory Panel) Spray Valves Closed (Panel FBF) Check Aux Spray Valve Closed Panel (Panel SFF) ! ATC Determine if SGs are Faulted

• Any SG Pressure decreasing in uncontrolled manner (Panel FBF)

• Any SG Completely depressurized (Panel ATC Determine if SG Tubes are

• Condenser Air Ejector Radiation recorder Trend (Rad Monitor Rack)

• SG Blowdown Recorder Trend (Rad Monitor Rack)

• Main Steam Line Radiation Recorders (Rack D-3 behind the Flight Panel)

• Any SG level increasing in an uncontrolled manner (Panel FBF) A TC Check if RCS is intact

• Containment Pressure Normal (Panel J-O or SBF-1)

• Containment Sump Level Normal (Panel J-O)

• Containment Radiation Normal o R-2 and R-7(Rack D-1 Behind Flight Panel} U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all Sf Pumps results in FR-C.2 Page 19 of35 Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: Event

Description:

BOP Actions during E-O (Procedure RO-1) .,..,. Position Examinee's Actions or Behavior BOP Monitor Control Room Alarms

• Acknowledge Supervisory Alarms

• Report Unusual Alarms

• Monitor High Containment Temp alarm (SCF)

• Monitor 480 Safeguards Undervoltage alarm BOP Verify SI Pumps

• Three SI Pumps (SBF-2)

• Two RHR Pumps (SBF-1 or BOP Verify Containment FCU

• Check all FCU running

• Place Damper Control Switches in Incident Mode (Panel SBF-2) o Damper AlB Closed o Damper C Closed o Damper D Open

• Place Control Switches for 1104 and 1105 to Open (Panel SBF-1)

• Check 1104 and 1105 BOP Verify SI Valve Alignment Proper Emergency

• Safeguards Valve Off Normal alarm CLEAR

• Ensure following OPEN o BIT Discharge 1835A1B (Panel SBF-2) o BIT Inlet 1852A1B (Panel SBF-2) o High Head Stop Valves 856J, H, C, E (Panel SBF-2)

• Check if MSIVS should remain OPEN o High Steam Flow SIIHi-Hi VC Pressure Alarm Clear (FDF)

• IF RWST Purification Loop in service contag!-=-N'-'-P--=O=--=-=to:....:s::..::e=-=c'-=u'-"re'-'-.

_____-I BOP Verify Aux Boiler Feed Pump Status

• Check Motor Driven Pumps Both Running

• Check Turbine Pump Running U3 NRC Scenario 4. PT -404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 20 of35 Appendix D Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: Event No.: Event

Description:

BOP Actions during E-O (Procedune RO-1) Time Position Examinee's Actions or Behavior BOP Verify Aux Feed Valve Alignment

• Motor driven AFW Pumps (Panel SCF) o Set 40SA -D to full open (Panel SCF)

• Check SG Blowdown isolation valves CLOSED (Panel SCF) BOP Check CCW Pumps

• All 3 Pumps Running

• Check RHR HX CCW Shutoff Valves Open 822A1B JPanel SGF} BOP Check Essential Service Water Pumps -3 Running BOP Verify Containment Ventilation Phase A & B (Panel SNF)

• Phase A actuated

• Phase B Actuated

• Check Phase A valve CLOSED

• Check Phase B valves BOP Verify Containment Ventilation

• Purge Valves CLOSED o FCV-1170 -117'3 (Panel SLF)

• Pressure Relief Valves CLOSED o PCV-1190 -1192 (Panel SLF)

• Check WCCPP Low Pressure Zone Alarms NOT Lit. !

• Verify IVSWS Valves OPEN o IV-AOV-1410,IV-AOV-1413 o IV-SOV-S200, BOP Verify Emergency Diesel Generator

• Check ALL EDGs RUNNING (Panel SBF-2)

• Check EDG Outlet Flow Control Valves OPEN o FCV-117S/177SA (Panel SBF-2) U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod wi II fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 21 of35 II Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: --+/--Event No.: i Event

Description:

BOP Actions during E-O (Procedure RO-1} Time Examinee's Actions or Behavior BOP Verify Control Room Ventilation Set Control Room Ventilation Control Switch to 10% incident mode (By Supervisory Panel Entrance) Check Damper Status 0 A--Dim 0 B --Bright 0 Either F1 or F2 Bright 0 Dampers D1 ancl D2 Bright Verify AlC Compressors and fans ALL Running 0 ACC 31A1B ON I3right 0 ACC 32 AlB ON Bright 0 ACF 31/32 ON Bright BOP Verify Emergency DC Oil Pump Status Main Turbine Emergency Bearing Oil Pump Running (Panel SEF) Dispatch NPO to verify Main Gen Air Side Seal Oil Pump Running

• MBFP DC Emergency Oil Pump Running (Alarm Panel SDF) BOP Reset Safety Injection Press both SI Reset buttons (Panel SBF-2) Check SI Reset 0 SI Actuated light BOP Reset If RCS pressure is < 360 psig place Makeup Control Switch to stop Dispatch NPO to secure VC Sump and RCDT Pumps on Waste Disposal Panel Dispatch NPO to align and reset MCC per SOP-EL-15 U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 22 of35 Appendix Scenario IOutline Form ES*D*1 Op-Test No.: _1_ Scenario No.: Event No.: Event

Description:

BOP Actions during E-O (Procedure RO-1) Time Examinee's Actions or Behavior BOP Check if additional actions should be performed If transition to ES-1.1 0 Inform CRS of Automatic Action Verification 0 Do not perform additional steps If Not transition to ES-1.1 0 Inform CRS of Automatic Action Verification 0 When transition out of E-O then continue U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 23 of35 i Appendix Scenario Outline Form Op-Test No.: _1_ Scenario No.: Event No.: 5 Continued Event

Description:

Procedure E-1 Time Position Examinee's Actions or Behavior Approximately 30 minutes after the A TWS event ReS inventory will be low enough to require a transition to FR-C.2 ATC Check if RCPs should be stopped

• At least 1 HHSI Pump running (Panel SBF-2)

• Subcooling

< value in table (QSPDS Monitor on desk) Stop All ATC Determine if SGs are Any SG Pressure decrealsing in uncontrolled manner (Panel FBF)

• Any SG Completely depressurized (Panel FBF) Check Faulted SG Isolated (Unless needed for cooldown) MSIVs (Panel SBF-1) MSIV Bypasses (Report from NPO) Main Feed Ref Valves or MOVs (2 is True on SNF or Panel SCF for MOVs) Bypass Feed Reg Valves or MOVs (Panel FBF or Panel SCF for MOVs) AFW to SG (Panel SCF) SF Atmospherics (Panel FBF) SG Blowdown Isolation (Panel SCF) SG Blowdown Sample V;alves (Panel SNF) SG Traps (Report from NPO) 32 SG affected Check MS-41 shut (NPO Report)

• 33 SG Affected Check MS-42 Shut (NPO Report) ATC/BOP Check Intact SG Levels

• Check Level Response in all SGs Normal (Panel FBF)

• Control Feed Flow to maintain 9 [14] -50% U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sf Fails; Loss of all SI Pumps results in FR-C.2 Page 24 of35 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: 5 Continued Event

Description:

Procedure E-1 ATC/BOP Reset SI Check RO-1 Steps 2 -'12 complete (report from BOP) Press both SI Reset Pushbuttons (Panel SBF-2) Check SI Reset o SI Actuated Light Extinguished (Panel i ATC/BOP Reset Phase A and Place switches for 200 A. B. C in Close (Panel SF F) Depress Phase A Reset pushbuttons (Panel SNF) Depress Phase B Reset pushbuttons (Panel SNF) CRS Check Secondary Check Seismic Event NOT occurred (Alarm on SDF Clear) Direct Watch Chemist to Sample SGs Direct Watch HP to perform contact surveys steam lines & blowdown lines Reset SG Sample Valves Place Blowdown Switches to Close Press SG Blowdown & Sample Valves Reset Push buttons 17 -24 on Panel SMF Check secondary radiation R-15 (Radiation Monitor Control Cabinet R-19 (Radiation Monitor Control Cabinet R-62 A-D (Rack D3 Behind Flight Panel)

• Check level in isolated SGs Stable (Panel ATC Check PRZR PORVs and Block Check Power Available to Block Valves Check Breakers for MCC-36NB closed (Panel SBF-2) Check Block Valves both energized (Panel FBF) Check PORVs Closed (Panel FCF) Open one Block Valves (Panel FCF) U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 25 of35 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: 5 Continued Event

Description:

Procedure E-1 I Establish Instrument Air to Containment

• Check Inst. Air Low Alarm Clear (Panel SJF)

• Press Inst. Air Reset Pushbutton 28 (Panel SMF)

• Open IA-PCV-1228 (Panel ATC/BOP Check RCP Seal

• Seal Injection Established (Panel SAF) OR I

• Bearing Coolant Low Flow Alarm Clear (Panel SGF) i

• Thermal Barrier CCW Header Low Flow alarm Clear (Panel SGF) ATC/BOP Check CCW for Charging Pump Available

• Check Pumps operating (Panels SBF-1 or SGF) ATC Determine if Charging Flow Has Been Established

• Check LCV-112B and LCV-112C both energized and one open (Panel SF F)

• Check CH-AOV-204B Open (Panel SF F)

• Check HCV-142 Fully Open (Panel SFF)

• Check/Start a Charging PumQ (Panel FBF) CRSATC Check if SI should be

• Subcooling

> 40°F [Table for Adverse] (QSPDS Monitor on Desk) Secondary Heat Sink 0 Total Feed Flow> 365 gpm Available (Panels SCF) 0 SG Level> 9% [14%) (Panel FBF) RCS Pressure 0 > 1700 psig [2000] (Panel FDF) 0 Stable or Increasing

!

• Pressurizer Level> 14% [32%1 (Panel FBF) U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all Sl Pumps results in FR-C.2 Page 26 of35 Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.: 5 Continued Event

Description:

Procedure E-1 CRSATC Check if Spray Pumps should be Check Any spray pumpl> running (Panel SBF-1) Check if Spray should be secured 0 5 Fan Cooler Units Running (Panel SBF-2) OR Containment Pressure < 16 psig (Panel SBF-1) Depress Containment Spray Reset push buttons (Panel SBF-1) Check Containment Radiation Normal 0 R-2 and R-7 (Rack 0-1 Behind Flight Panel) Stop Containment Spray Pumps and place in auto (Panel SBF-1)

• Close Pump discharge valves 866 AlB (Panel SBF-1) BOP Determine if RHR Pumps should be stopped Check RCS Pressure>

360 psig (Panel FDF or SFF) Check RCS Pressure stable or increasing

• Check any RHR pumps running with suction to RWST (Panel SBF-1) I

• Stop RHR Pumps and place in Auto (Panel SGF) ATC I Check for Faulted SG I

• Check pressures in all SG stable or increasing (Panel FBF) i

• Check RCS pressure stable or increasing BOP Determine if Diesel Generators should be stopped 480V buses energized by offsite power (Panel SHF) Dispatch NPO to shutdown EDGs ! BOP Evaluate Plant Status

• CRS directs BOP to Attachment 1 ATC Check if RCS Cooldown and Depressurization is Required Check RCS pressure Greater than 360 (Panel FDF or SFF) OR Check RTHR Pump Flow Less than 300 gpm (Panel SBF-2)

• CRS Transition to ES-1.2 Post LOCA Cooldown and Depressurization U3 NRC Scenario 4, PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 27 of35 i Appendix Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: -A.... Event No.: 5 Continued . Event

Description:

Procedure E-1 ATC/BOP I Determine if Transfer to Cold Leg Recirc is required.

i

• Check RWST Level < 11.5 feet (Panel SBF-1 or SBF-2) BOP Check at least one recirc flowpath using Recirc Pumps Available

• 31 or 32 Recirc Pump Available (Panel SBF-1)

• Discharge Valves 1802A or B Open (Panel SBF-1) 31 RHR Heat Exchanger 0 822A Open/Available 0 638 Open/Available 0 747 Open/Available 0 899B Open/Available 0 888A AND 888B Both Closed 0 745A AND 745B Both Open OR 32 RHR Heat Exchanger

• 0 822B Open/Available 0 640 Open/Available 0 746 Open/Available 0 899A Open/Available 0 888A AND 888B Both Closed

• CCW System and at least 1 CCW Pump Available

!

• At least 1 Non Essential Service Water Pump Available

• MCC36A or MCC36B Energized U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaJigned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 28 of35 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: 5 Continued Event

Description:

Procedure E-1 Check at least one recirc flowpath using RHR Pumps Available 31 or 32 RHR Pump Available (Panel SBF-1) Containment Sump to RHR Pumps 885A AND 885B Open/Available (Panel SBF-1) 744 and 882 Available 31 RHR Heat Exchangef 822A Open/Available 638 Open/Available 747 Open/Available 899B Open/Available 888A AND 888B Both Closed 745A AND 745B Both Open 32 RHR Heat Exchanger 822B Open/Available 640 Open/Available 746 Open/Available 899A Open/Available 888A AND 888B Both Closed CCW System and at least 1 CCW Pump Available At least 1 Non Essential Service Water Pump Available MCC36A or MCC36B Ener ized U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 29 of35 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: 5 Continued Event

Description:

Procedure E-1 Check at least one recirc flowpath using High Head SI Pumps Available

• One HHSI Pump Available (Panel SBF-1) One Recirc or RHR Pump capable of supplying HHSI Pump 0 1802A or B Available if using Recire 0 885A AND 885B Available If using RHR (Panel SBF-1) 31 RHR Heat 0 822A Open/Available 0 638 Open/Available 0 747 Open/Available 0 899B Open/Available 0 888A AND 8888 Both Closed 0 745A AND 7458 Both Open OR 32 RHR Heat 0 822B Open/AvClilable 0 640 Open/Available 0 746 Open/Available 0 899A Open/Available 0 888A AND 8888 Both Closed High Head Valves Available 0 744 AND 882 Available 0 842 OR 843 Available 0 887 A AND 88713 Available 0 851A OR 851 B Available 0 1810 Available 0 743 OR 1870 Available 0 850A AND 850C Available if 31 HHSI Pump to be used 0 1852A OR 18528 Available if 32 or 33 HHSI Pump to be used 0 1835A OR 1835B Available if 32 or 33 HHSI Pump to be used 0 1813 Available U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on 8us 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 30 of35 Appendix Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.: 5 Continued Event

Description:

Procedure E-1

• CCW System and at least 1 CCW Pump Available

• At least 1 Non Essential Service Water Pump Available

• MC936A or MCC36B Energized CRS

• IF unable to verify 1 low-head or 1 High-head Recirculation Flowpath Available, Transition to . BOP Determine if PAB Conditions

• R-64, 55 Ft Elev CompOSite PAB

• R-65, 73 Ft Elev CompOSite PAB

• R-66, 34 Ft Elev Composite PAB

• R-67, 41 Ft Elev Composite PAB

• R-68, 15 Ft Elev CompOSite PAB

• R-69, 54 Ft EI Pipe Pen Comp

• PAB & TRENCH AREA HI TEMP alarm on SDF NOT LIT CRS/BOP IF PAB Radiation Is NOT Normal

• Try to identify and isolate leakave

• If loss of RCS outside Cc)ntainment is in Transition to ECA-1.2 CRS/BOP Direct Watch Chemist to sample: Ruptured 0 0 RCS 0 Activity 0 Boron 0 Hydrogen Containment Atmospere 0 Activity 0 Hydrogen Recirc 0 0 0 0 U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sl Fails; Loss of all Sf Pumps results in FR.*C.2 Page 31 of35 Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.: 5 Continued Event

Description:

Procedure E-1 CRS/BOP Determine availability of the following:

• Charging Pumps

• Safety Injection Pumps

• RHR Pumps

• Recirc Pumps

• Auxiliary Feedwater Pumps

• Component Cooling Water Pumps

• Service Water Pumps

• Containment Spray System

• Containment Isolation System

• Hydrogen Recombiner

• Fan Cooler Units

• PAB Exhaust Fans

• Diesel Generators

• Offsite Power

• 480V Safeguards Buses

• 125V Batteries

• Instrument Air System and PORV Nitrogen Backup BOP . Place Hydrogen Monitoring System in service .. _______--I BOP/CRS I Notify Emergency Director of any systems/Equipment NOT available.

U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank 0 rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip successful; Auto Sl Fails; Loss of all SI Pumps results in FR-C.2 Page 32 of35 Appendix Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.: Event Descri tion: Degraded Core Cooling FR-C.2 Time Examinee's Actions or Behavior CRS Transition to BOP

• Verify SI Valve Alignment !

• Attachment 1 Injection phase SI Valve Lin--=e...;cu-"--

__________

-11 BOP/ATC Verify SI Flow in all Trains

• Check High Head Flow Indicated o No Flow Indicated o Establish Maximum Charging with all Available Pljm=p-=..s

__ ----11 Check RCS Pressure Less Than 360 psig to check if RHR should be verified . . Pressure is greater than 360. ATC Check RCS Vent Path

• Check Power to PORV Block Valves o Power is NOT available to MOV-535

• Valve was open when bus de-energized

• Expect valve OPEN

• Check PORVs Closed

• Check Block Valves at least one OPEN . Check RCP Status

• All RCPs should be BOP i Check Core

• Check RVLlS Full Ranqe NOT greater than BOP Check power to accumulator isolation valves

• Power available o Discharge NPO to energize valves

• Dischar e valves OPEN U3 NRC Scenario 4. PT-404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, A TWS Local trip successful; Auto Sf Fails; Loss of all SI Pumps results in FR-C.2 Page 33 of35 Appendix Scenario Outline Form ES-D-1 A TC Check intact SG levels Any greater than or equal to 9% I ncrease feed flow to restore narrow range level> 9% in at least one SG

• Control feed flow to maintain level between 9 and 50% ATC Depressurize All Intact SG to 175 psig Maintain cooldown rate in RCS cold legs < 100°F/hr Dump steam to condensers If condensers not available Manually open SG Atmospherics Check SG pressure < 175 and Temp < 390 0 Lead Examiner Terminate scenario when cooldown established.

U3 NRC Scenario 4. PT -404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto S( Fails; Loss of all S( Pumps results in FR-C.2 Page 34 of35 Appendix 0 Scenario Outline Form ES-D-1 Post Scenario Event Classification Event Classification

-Site Area Emergency EAL 1.1.2 RED path in F-O.1 Subcriticality AND ALL manual attempts at tripping the reactor from the control room have failed to reduce power range < 5% Also possible:

EAL-1.2.1 ORANGE or RED path in F-O.2 CORE COOLING U3 NRC Scenario 4. PT -404 Failure High -Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sl Fails; Loss of all SI Pumps results in FR-C.2 Page 35 of35