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Text

Initial Exam 2011-301 Draft Administrative JPMs
	ML112660276
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Site:	Harris
Issue date:	09/22/2011
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References
	05-400/11-301
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{{#Wiki_filter:Appendix C Job Performance Measure Form ES-C-i

                                             -    Worksheet Facility:                Shearon Harris                         Task No.:     301 005H401 Task Title:              Determine Rod Misalignment Using       JPM No.:      2011 NRC JPM Thermocouples                                        RO Al-i K/A

Reference:

G2.17 4.4 /4.7 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testinci: 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: The plant was at 90 percent power, with a load decrease in progress, when the CRS noticed that the DRPI indication for rod H02 was reading 24 steps higher than the group demand. The load decrease has been stopped and AOP-OOi entered. Initiating Cue: The CRS has directed you to calculate the temperature difference between thermocouple(s) adjacent to the misaligned rod and the average of symmetric thermocouple(s), using Attachment 2 of AOP-OOi and the provided TIC Core Maps. 2011 NRC Admin Exam ROA1-1 Rev. 1

Appendix C Job Performance Measure Form ES-C-i

 .                                           Worksheet Task Standard:      All calculations within +/- 2° of actual.

Required Materials: Calculator General

References:

AOP-00i, Attachment 1 and Attachment 2, Rev. 35 Handouts: JPM Cue Sheets Pages 10-11 AOP-001, Attachments 1 and 2, (Rev. 35) Time Critical Task: No Validation Time: 12 minutes Critical Task Justification If the wrong thermocouples are used then none of the results will be Step 2 correct If the wrong values are selected then none of the results will be correct Step 3 If the calculation for the averages were incorrect the results will be Step 4 incorrect If the differences are calculated incorrectly then the candidate will come Step 5 to the wrong conclusion for Tech Specs 2011 NRC Admin Exam RO Al-i Rev. 1

Appendix C Page 3 of 12 Form ES-C-i

                      -    VERIFICATLON OF COMPLETION           -

Start Time: Performance Step: 1 OBTAIN PROCEDURE (provided with handout) Standard: Obtains AOP-OO1 and refers to Affachments 1 and 2. Comment: v Performance Step: 2 DETERMINE THERMOCOUPLE LOCATION(S) ADJACENT TO THE MISALIGNED ROD USING THE CORE GRID MAP (SHEET 1), AND CIRCLE LOCATION(S) IN TABLE ABOVE. THESE THERMOCOUPLES(S) ARE AFFECTED. Standard: Using the core grid map (Attachment 2, page 1 of 2), Determines affected thermocouples to be G02, J02, and H03. Circles G02, J02, and H03 on the table (Attachment 2, page 2 of 2). Comment: V Denotes Critical Steps

  -                                             2011 NRC Admin Exam RO Al-i Rev. 1

Appendix C Page 4 of 12 Form ES-C-i

VERIFICATION OF COMPLETION - V Performance Step: 3 RECORD VALUES FOR ALL OPERABLE AFFECTED AND SYMMETRIC THERMOCOUPLES USING THE RVLIS CONSOLE OR ERFIS. SYMMETRIC THERMOCOUPLES ARE THOSE IN THE SAME ROW. Standard: Locates RVLIS Console and accesses T/C CORE MAP for Train A and Train B. (Printout of RVLIS core map provided in handout) Records value for Affected TC G02 (652°F) and Symmetric TC P07 (636°F). Records value for Affected TC J02 (652°F) and Symmetric TC P07 (636°F). Records value for Affected TC H03 (649°F) and Symmetric TCs C08 (636°F), H13 (640°F), and N08 (644°F). Comment: V Performance Step: 4 DETERMINE THE AVERAGE OF SYMMETRIC THERMO COUPLES, FOR EACH AFFECTED THERMOCOUPLE. Standard: Determines (636°F) for G02s Symmetric TC Determines (640°F +/- 2°F) for H03s Symmetric TC Determines (636°F) for J02s Symmetric TC Comment: If the candidate includes the adjacent TCs with the EXAMINERS NOTE: Symmetric TC numbers the averages will be wrong and the end result will be that a wrong final difference will be given: Determines (644°F) for G02s Symmetric TCs Determines (640°F) for H03s Symmetric TCs. Determines (644°F) for J02s Symmetric TCs. 7- Denotes Critical Steps 2011 NRC Admin Exam RO Al-i Rev. 1

Appendix C Page 5 of 12 Form ES-C-i

      - -
                          -      V1FITlOOF COMPLETION                        -

V Performance Step: 5 CALCULATE THE DIFFERENCE BETWEEN EACH AFFECTED THERMOCOUPLE AND THE AVERAGE OF ITS SYMMETRIC THERMOCOUPLES. Standard: Calculates difference of 16°F 16°F for TC G02 9°F for TC H03 16°F forTCJO2 (+/- 2°F between all affected TCs and their symmetric TCs.) Reports that temperature difference is greater than 10°F. Evaluator Cue: CRS acknowledges report. END OF JPM Comment: Stop Time: Terminating Cue: Difference between each affected thermocouple and its symmetric thermocouples has been calculated. EXAMINERS NOTE: If the candidate included the adjacent TCs with the Symmetric TC numbers the averages would have been wrong and the calculated difference would be 8°F. The report would be that the temperature difference is less than 10°F. This report would provide the CRS with inaccurate information. V - Denotes Critical Steps 2011 NRC Admin Exam RO Al-i Rev. 1

Appendix C Page 6 of 12 Form ES-C-i

                               -       VERIFICATION OF COMPLETION KEY I                MALFUNCTION OF ROD CONTROL AND INDiCATION SYSTEM                             I Attachment 2 Adjacent and Symmetric Thermocouple Locations
                                   -

Sheet 1 of3 THERMOCOIJPLE LOCATIONS 1 2 3 4 5 7 8 9 10 11 12 3 14 15 I I I I I I I I I

A .- .-

B I ---*-- p c --L* ft T ft i ------- i D T ft ft E ft T ft T T T T F R V R T R T R T R T G ft T ft ft ft T H c) 7 ft r T ft 1 ft ft T T ft ft T ft T ft RT ft ft ft K L I ft F ft M T ft ft T ft T R N T T R T R T p ft T ftT ft R T R Control Rod

T Thermocouple

         -
            - Thermocouples aban-doned by EC 47997 AOP-OO1                                       Rev. 35                         Paae $1 of 47 V Denotes Critical Steps
 -                                                             2011 NRCAdmin Exam ROA1-i Rev.i

Appendix C Page 7 of 12 Form ES-C-i

      .                               VERI-FICATION OF COMPLETION KEY I                 MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM                            I Attachment 2 Adjacent and Symmetric Thermocouple Locations
                                   -

Sheet 2 of 3 NOTE e 610. E07. HUB. K08, and PUB have no symmetric locations. e Symmetric thermocouples are those in the same row. SYMMETRIC LOCM9O4S GRID II IV TRAIN A B A B A B A B AU8 GOlk G15 R07 S L 805 E14 L14* Y 0 008 H13 NOB (Hop M C D03 C12 N04 03 M A E04 D05 E12 Mu L12 E T Hil £08 L08 H05 T I F05 Fil £10 K11* KOS LC6 R 0 F03* F13 N10 N06 K03 I N G06 FU9 110 C s GOB H09 o (J02) 07 M09 J12 Th-erniocou pies abandoned by EC 47997

1. DETERMINE thermocouple location(s) adjacent to the misaligned rod using core grid map (Sheet Ii:) CIRCLE location(s) in Table above AOP-0O1 Rev. 35 Page 42 of 47 V - Denotes Critical Steps 2011 NRC Admin Exam RO Al-i Rev. 1

Appendix C Page 8 of 12 Form ES-C-i VERIFICAT[ONOF COMPLETIOr4 - KEY TIC CORE MAP (DATA SHEET 1) TRAIN B MSG #245 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A I A B 632 I B C C D 1636 650 E I 644 50 640 632 1 E F 50 644 I F G 150 644 632 HI 644 H 640 50 jj K I 640 I K L I__ 644 640 644 50 L M 636 N 640 N P I P R 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 TRAIN A TIC CORE MAP MSG # 245 A A B B C C D D E E F F G G H H J J K K L L M M N N P P R R 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 KEY if - Denotes Critical Steps 2011 NRC Admin Exam RO Al-i Rev. 1

Appendix C Page 9 of 12 Form ES-C-i .

                                 -     VRIF[CATIQF4OFCOMPLETION                               -

I MAISUNCTION OF ROD CONTROL AND INDICATION SYSTEM I Attachment 2 Adjacent arid Symmetric Thermocouple Locations

Sheet 3 of 3

2. RECORD the follothng in the table below:

Adjacent TO number
Adjacent TO value using the RVLIS Console, ERRS, or OSI-PI
Symmetric TC nunibers (not including adjacent TCs)
Symmetric TO values for all OPERABLE TOs using the RVLIS Console, ERNS, or OSI-PI

3. DETERMINE the average of symmetric thermocouples, for each adjacent thermocouple.

Adjacent TO Symmetric TO Symmetric TO Number Value Number Value Average J02 P07 C02 G52 COS M1 4O H03 49 N08 G44 G40 Q02 N/A P07 $3G J02 62 63

4. COMPARE each aacent thermocouple vaiue listed to its symmetric thermocouple average for indication of a misaligned rod. (REFER TO Attachment 1 )

                                         --END OF AT[ACHMENT 2--

AOP-0O I I Rev. 3 I Pane 43 of 47 V - Denotes Critical Steps 2011 NRCAdmin Exam ROA1-1 Rev.1

Appendix C Page 10 of 12 Form ES-C-i

                   .         VTONOMPLETION                           -

Job Performance Measure No.: 2011 NRC JPM RO/SRO Al-i DETERMINE ROD MISALIGNMENT USING THERMOCOUPLES Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: V - Denotes Critical Steps 2011 NRC Admin Exam RO Al-i Rev. 1

Appendix C Page ii of 12 Form ES-C-i

                   -
                     -            JPMCUESI-[EET Initial Conditions:   The plant was at 90 percent power, with a load decrease in progress, when the CRS noticed that the DRPI indication for rod H02 was reading 24 steps higher than the group demand. The load decrease has been stopped and AOP-00i entered.

Initiating Cue: The CRS has directed you to calculate the temperature difference between thermocouple(s) adjacent to the misaligned rod and the average of symmetric thermocouple(s), using Attachment 2 of AOP-001 and the provided T/C Core Maps. 2011 NRC Admin Exam ROA1-1 Rev. 1

_______ ____ Appendix C Page 12 of 12 Form ES-C-i

                             .              JPMCUE-SHEET TIC CORE MAP (DATA SHEET 1) TRAIN B                                                         MSG #245 1      2       3   4       5   6   7      8   9      10  11     12  13       14     15 A                                                                     I                            A B                               1                            632      I                            B C                                                636                               I               C D                 1636            650                                              I E           I                                    644         50         640          6321          E F                     50          644                                                    I_______  F G     150                                        644                                        632  G 1

H 649 644 J 640 50 K 640 I K L 644 640 644 50 L M 636 I M N 640 N P 636 I P R A 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 TRAIN A T/C CORE MAP MSG # 245 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A I 50 A B ]636 I B C 632 I C D I D E I 636 640 1 E F 644 648 644 F G I 652 640 H I 640 644 652 640 640 I H 652 K 640 644 50 K L M I 640 644 I M N 636 640 644 1 N I 640 I P R I 636 I A 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 2011 NRC Admin Exam RO Al-i Rev. 1

Appendix C Job Performance Measure Form ES-C-i Worksheet Facility: HARRIS Task No.: Task Title: Determine the Target Rod Height JPM No.: 2011 NRC Admin and the Boron Concentration JPM RO Al -2 Change Required for a Rapid Power Reduction lAW AOP-038 K/A

Reference:

2.1.25 (2.8/3.1) Examinee: Examiner: Facility Evaluator: Date: Method of testin: 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:

The plant is operating at 90% power, with RCS Boron at 250 PPM.
Core Burnup is at 425 EFPD
The Load Dispatcher just reported that a tornado has taken out a High Voltage Transmission tower on the grid.
The Load Dispatcher has requested HNP to rapidly reduce power to 65% and to reduce power at 25 DEH Units/minute.
The crew has entered AOP-038, RAPID DOWNPOWER.

Initiating Cue: The CRS has directed you to perform AOP-038, Step 3 Determine the

required boric acid addition for desired power reduction - -. Determine the final power target rod height, time in core life and the amount of boric acid that will be required. List each value on the space provided. 2011 NRC Admin Exam JPM RO A1-2 Rev. 1

Appendix C Job Performance Measure Form ES-C-i Worksheet Task Standard: Target Rod Height and Boration calculation within specified bands. Required Materials: Calculator General

References:

AOP-038, RAPID DOWNPOWER, Revision 26 Handout: AOP-038, Attachment 2, Rev. 26 Time Critical Task: No Validation Time: 10 minutes Critical Task Justification Determine Target If the wrong rod height is determined the boric acid addition for rod Rod Height insertion will not be adequate Determine Time In If the wrong time in core life were used the amount of boric acid addition Core Life would be incorrect. Since this is EOL using either MOL or BOL the determination would yield significantly less boric acid than required. Determine Required If the wrong amount of boric acid addition is calculated the rod height will Boric Acid Addition not be correct for the final plant power level 2011 NRC Admin Exam JPM RO Al -2 Rev. 1

Appendix C Page 3 of 8 Form ES-C-i

 .                            PERFORMANCE INFORMATION STARTTIME:

AOP-038, Step 3 Performance Step: 1 Reviews Step 3 Standard: Determines RNO applies and proceeds to Attachment 2. Evaluator Cue: Provide handout or, if in the simulator, the applicant can pull the procedure. Comment: AOP-038, Attachment 2 V Performance Step: 2 Determine Target Rod Height Standard: Target Rod Height at 65% power 70 60% Power: CB D @171-183 steps. 183171 =12/2=6 171 +6=l77steps Comment: AOP-038, Attachment 2 V Performance Step: 3 Determine Point in Core Life Standard: Compares current RCS Boron/Core Burnup to table and determines EOL. 425 EFPD = EOL Comment: V - Denotes Critical Steps 2011 NRC Admin Exam JPM RO A1-2 Rev. 1

Appendix C Page 4 of 8 Form ES-C-i - - PFQRANCE INFORMATION AOP-038, Attachment 2 V Performance Step: 4 Calculate Boron Change. Standard: Applies divide by two NOTE for the 5% increment (70% to 60%) and the 10% increment totals in the EOL Column: 202 + 203 + (180/2) 495 ( 490 500 gallons) Comment: AOP-038, Step 3 Performance Step: 5 Reports Step 3 completion to CRS. Standard: Reports results of calculation. Evaluator Cue: Acknowledge report. Comment: Terminating Cue: After the Step 3 results report: Evaluation on this JPM is complete. STOP TIME: V - Denotes Critical Steps 2011 NRC Admin Exam JPM RO Al -2 Rev. 1

Appendix C Page 5 of 8 Form ES-C-i PERFORMANCE lNFOlMAT[ON KEY Power Reduction JAW AOP-038 90% 65%

RAPID DOWNPOWER Attachment 2 Sheet 1 of 1 Gallons of Boric AcidTarget Rod Height Required for Power Reduction NOTE

        . This Attachment serves as a ye actMty p[an [C.3]
        . This table applies to Cycle 17 only.
        . Target rod heights correspond to the low& (target) power level in each row.
        . Gallons of boric acid in the table are for 10% power reduction increments, These are additive for power reductions of greater thar 10%.

Example: A power reduction from 90% to 60% at BOL would require [181 gal ÷ 163 gal +155 al = 499 galJ

        . For purposes of this procedure, 5% increments can be obtained by dividing by two.
        . As used in this table, the following times in core life are assumed:

BOL (0 EFPD i61 )(3000 MWD/MTU) MOL (161 < EFPD 333) (10,000 MWD1MTU) EOL (333 < EFP[) 507) (17,000 MWDIMTU) j (425 BFPD) Power Target Gallons of Boric Acid Required for Power Reduction Level Rod (%) Height BOL MOL EOL (D Bank) 0 EFPD 113i 161 K EFPD 333 333< EFPD 501 lOOtoSO 206 216 264 317 90 to 80 194 181 214 202 80to70 183 163 169 203 70 to 60 171 155 173 180/2 = 91) 60 to 50 159 146 173 189 50 to 40 147 155 157 205 40 to 30 135 156 166 206 30 to 20 124 166 166 255 20 to 10 1 12 157 175 312

                                         --END OF AT[ACHMENT 2_

AOP-038 I Rev. 26 Page 21 of 24

 - Denotes Critical Steps                                 2011 NRC Admin Exam JPM RO A1-2 Rev. 1

Appendix C Page 6 of 8 Form ES-C-i

                             \JAIEIOATION OF COMPLETION Job Performance Measure No.:  2011 NRC Admin JPM RO A1-2 Determine the Target Rod Height and the Boron Concentration Change Required for a Rapid Power Reduction lAW AOP-038 Examinees Name:

Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: 2011 NRC Admin Exam JPM RO Al -2 Rev. 1

Appendix C Page 7 of 8 Form ES-C-i .- JPlifCUESF-1ET Initial Conditions: . The plant is operating at 90% power, with RCS Boron at 250 PPM.

Core Burnup is at 425 EFPD

                                 . The Load Dispatcher just reported that a tornado has taken out a High Voltage Transmission tower on the grid.
                                 . The Load Dispatcher has requested HNP to rapidly reduce power to 65% and to reduce power at 25 DEH Units/minute.

The crew has entered AOP-038, RAPID DOWNPOWER.

Initiating Cue: The CRS has directed you to perform AOP-038, Step 3 Determine the required boric acid addition for desired power reduction - Determine the final power target rod height, time in core life and the amount of boric acid that will be required. List each value on the space provided. NAME DATE Target rod height = CBD at steps Time in core life used = Required boric acid addition = gallons 2011 NRC Admin Exam JPM RO Ai-2 Rev. 1

Appendix C Page 8 of 8 Form ES-C-i JPMCUE SHEET RAPID DOWN POWER Attachment 2 Sheet I of I GaIlons of Boric AcidlTarget Rod Height Required for Power Reduction NOTE

This Attachment serves as a readllvity plan. tC31
This table applies to cycle 17 onIy
Target rod heights correspond to the lower (target) power level in each row.
Gallons of boric acid in the table are for 10% power reduction incrementa These are additive for power reductions of greater than 10%.

Example: A power reduction from 90% to 60% at BOL would require [181 gal + 163 gal --i5 gal 499 galj a For purposes of this procedure, 5% increments can be obtained by dividing by two.

   . As used in this table, the followiftg times in core life are assumed:

80L (0 EFPD 161) (3Q00 MWD/MTU) MOL (161 < EFPO 333) (10,000 MWDIMTU) OL (333 < EFPD 507) (17,000 MWD/MTU) Power Target Gallons of Boric Acid Required for Power Reduction Level Rod (%) Height BOL MOL EOL (D Bank) 0 EFPD 161 161 < EFPD 333 333 < EFPD 507 100 to9O 206 216 264 317 O to 80 194 181 214 202 80to70 183 163 189 203 70to60 171 155 173 180 60 to 50 159 146 173 189 50 to 40 147 155 157 205 40 to 30 135 156 166 206 30 to 20 124 166 166 255 20 to 10 112 157 175 312

                                    --END OF ATTACHMENT 2 AOP-038                         I                Rev. 26                                Page 21 of 24 2011 NRC Admin Exam JPM RO Ai-2 Rev. 1

Appendix C Job Performance Measure Form ES-C-i

                                  -                Worksheef Facility:               HARRIS                                  Task No.:

Task Title: Review the Completed OST for JPM No.: 2011 NRC RO A2 Auxiliary Feedwater Pump 1 B-SB K/A

Reference:

2.2.12 (3.4) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testinci: 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:

The plant is operating at 100% power OST-i 076, AUXILIARY FEEDWATER PUMP lB-SB OPERABILITY TEST QUARTERLY INTERVAL MODES 1-4, has just been completed Initiating Cue: You are the BOP and have been asked to peer check the just completed copy of OST-1076. Completely review the procedure and note any problems in the spaces provided.

2011 NRC Admin Exam RO A2 Rev. 1

Appendix C Job Performance Measure Form ES-C-i Wbrksheet Task Standard: All errors (4) identified Required Materials: None General

References:

OST-1076, AUXILIARY FEEDWATER PUMP 1A-SA OPERABILITY TEST QUARTERLY INTERVAL MODES 1-4, Rev. 29 Handout: Completed OST-1 076 with the errors incorporated. Time Critical Task: No Validation Time: 12 minutes Critical Task Justification Item 1 Identification of stopwatch beyond calibration date all timing data collected with out of cal device is non usable therefore the test is invalid. Item 2 Outboard Horizontal Vibration reading not documented with the

reading in the ALERT range the pump would still be operable but this could prevent corrective action or the required increase in surveillance frequency. Item 3 Shut time for valve 1AF-51 exceeding CODE CRITERIA. This valve should have been retested immediately but was not. 2011 NRC Admin Exam IRO A2 Rev. 1

Appendix C Page 3 of 6 Form ES-C-i PERFORMANCE INFOFMATiON START TIME: Performance Step: 1 Reviews the completed OST-1 076 for the 1 B-SB test. Standard: Ensures proper conditions, signatures/initials, and may verify the current revision of the procedure Comment: J Performance Step: 2 Review the completed OST Standard: Attachment 1 (Page 20) Identifies that the stopwatch that was

used is past calibration date Evaluator Note: This makes the OST invalid and/or any timed elements would have to be repeated. Comment: q Performance Step: 3 Review the completed OST Standard:

Attachment 3 (Page 24) Outboard Horizontal Vibration

reading is in the ALERT range but there is no documentation in accordance with Instructions l.a and 1 .b. Evaluator Note: The pump would still be operable but this could prevent corrective action or the required increase in surveillance frequency. Comment: V - Denotes a Critical Step 2011 NRC Admin Exam /RO A2 Rev. 1

Appendix C Page 4 of 6 Form ES-C-i

                            . PERFORMANCE lNFORMATlON              -

J Performance Step: 4 Review the completed OST Standard: Attachment 4 (Page 25) 1AF-51 SHUT time exceeds CODE

CRITERIA and, in accordance with Step 7.0.1, should have been retested immediately. Comment: Performance Step: 6 Review the completed OST Standard: Returns the procedure unsigned and has identified three errors during the peer check review. Comment: Terminating Cue: When the procedure is returned: Evaluation on this JPM is complete. STOP TIME: V - Denotes a Critical Step 2011 NRC Admin Exam JRO A2 Rev. 1

Appendix C Page 5 of 6 Form ES-C-i

VER[F1CAT1ON OF COMPLTlON Job Performance Measure No.: 2011 NRC RO A2 Review the Completed OST for Auxiliary

Feedwater Pump lB-SB Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: V - Denotes a Critical Step 2011 NRC Admin Exam %RO A2 Rev. 1

Appendix C Page 6 of 6 Form ES-C-i JRMCUESHE INITIAL CONDITIONS:

The plant is operating at 100% power

                            . OST-1076, AUXILIARY FEEDWATER PUMP lB-SB OPERABILITY TEST QUARTERLY INTERVAL MODES 1-4, has just been completed INITIATING CUE:              You are the BOP and have been asked to peer check the just completed copy of OST-1 076. Completely review the procedure and note any problems in the spaces provided.

NAME DATE IF any discrepancies were identified in the review of OST-1 076 list them on the lines below V Denotes a Critical Step

 -                                                      2011 NRC Admin Exam RO A2 Rev. 1

Appendix C Page 1 of 12 Form ES-C-i Worksheet Facility: Shearon Harris Task No.: Task Title: Using survey mars determine stay JPM No.: 2011 NRC Exam times Admin JPM RO A-3 AfSoSeO K/A

Reference:

G.2.3.4 RO 3.2 SRO 3.7 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: Two individuals are tasked to hang a clearance on 1 CS-38, Letdown PCV Isol vlv. The clearance includes the following valves:

1CS-35
1CS-36
1CS-37
1CS-38
1CS-39
1CS-40
1CS-43 Initiating Cue: Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1750 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Nine Mile Point earlier this year where he has accumulated 2550 mrem.

The clearance and work activity is for 1 CS-38, Letdown PCV Isol vlv. The ALARA group has determined that additional shielding is not warranted for this work. Using the supplied survey map, determine the maximum allowable individual stay times for each Operator that would prevent exceeding the Progress Energy Annual Administrative dose limit while performing these activities. Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance. Complete the information below and return to the evaluator when complete. 2011 NRC Exam Admin JPM RO A3 Rev. i

Appendix C Page 2 of 12 Form ES-C-i

                         -                  Worksheet Task Standard:      Calculation of stay times based on survey maps, two hours for Operator 1, six hours for Operator 2.

Required Materials: Survey map A45 RAB 236 LETDOWN & LETDOWN REHEAT HX &VG Map 21 SFD-5-S-1 304 General

References:

DOS-NGGC-0004 Progress Energy Annual Administrative Dose Limits Section 9.3 (Rev.12) LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non- Progress Energy dose for the current year has been determined. Time Critical Task: No Validation Time: 10 minutes Critical Task Justification Step 1 Must determine dose rates in order to calculate stay time Step 2 Must determine available dose to determine stay time. Step 3 IF incorrect calculation of stay time is made the individuals could exceed their dose limits. 2011 NRC Exam Admin JPM RO A3 Rev. 1

Appendix C Page 3 of 12 Form ES-C-i FEROMANCINFOAMAtlON START TIME: Evaluator Note: The order of performance does not matter IF THE APPLICANT ASKS FOR IT: Provide a copy of DOS NGGC-0004, Rev. 12 if Performance Step: 1 Using Radiological Survey Record Map A45 and RAB 236 LETDOWN & LETDOWN REHEAT HX &VG Map 21, determines dose rates in the area where the clearance will be applied Standard: Identifies that General Area Dose Rates are 125 mrem/hr Comment: if Performance Step: 2 Determine the remaining dose for the year for each individual Standard: Operator 1: 250 mrem 2000 mrem 1750 mrem

                                            -            = 250 mrem Operator 2: 450 mrem 4000 mrem 700 mrem (PE)
                                          -                 - 2550 mrem (NMP)  = 750 mrem Comment:

V - Denotes Critical Steps 2011 NRC Exam Admin JPM RO A3 Rev. 1

Appendix C Page 4 of 12 Form ES-C-i PERFOMANCE INFOMATIN V Performance Step: 3 Determine stay time for each operator (based on 1 St Operator reaching 2 Rem and the 2nd Operator reaching 4 Rem for the

year) Standard: Operator 1: 2 hours 250 mrem ÷ 125 mrem/hr = 2 hrs Operator2: 6 hours 750 mrem ÷ 125 mrem/hr = 6 hours Comment: Terminating Cue: After the stay time has been calculated, this JPM is complete. END OF JPM STOP TIME: V - Denotes Critical Steps 2011 NRC Exam Admin JPM RO A3 Rev. 1

Appendix C Page 5 of 12 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2011 NRC Exam Admin JPM RO A-3 Using survey maps

determine stay times. (DOS-NGGC-0004 Rev. 12) DOS-NGGC-0004 Progress Energy Annual Administrative Dose Limits Section 9.3. LIMIT 2 rem Progress Energy dose not to exceed 4 rem total dose if non- Progress Energy dose for the current year has been determined. Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: 2011 NRC Exam Admin JPM RO A3 Rev. 1

Appendix C Form ES-C-i JFMCUESHET Initial Conditions: Two individuals are tasked to hang a clearance on 1 CS-38, Letdown PCV Isol vlv. The clearance includes the following valves:

                        . 1CS-35

1CS-36
1CS-37

                        . 1CS-38
                        . 1CS-39
                        . 1CS-40

1CS-43 Initiating Cue: Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1750 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Nine Mile Point earlier this year where he has accumulated 2550 mrem.

The clearance and work activity is for 1 CS-38, Letdown PCV Isol vlv. The ALARA group has determined that additional shielding is not warranted for this work.. Using the supplied survey map, determine the maximum allowable individual stay times for each Operator that would prevent exceeding the Progress Energy Annual Administrative dose limit while performing these activities. Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance. Complete the information below and return to the evaluator when complete. Name Record the maximum allowable stay time calculations below to the nearest hour and minute. Operator 1: Operator 2: 2011 NRC Exam Admin JPM RO A3 Rev. 1

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Appendix C Form ES-C-i JPM CUE SHEET RAB 236 LETDOWN & LETDOWN REHEAT MAP 21 HEAT EXCHANGERS/VALVE GALLERY 5S Gw4r4,

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Appendix C Form ES-C-i JPM CUE SHEET Map A45 RADIOLOGICAL SURVEY RECORD I I Unit I. BIdg/1cv: RAB 236 Area: LetclownNX & VG jL)sk: 07/01111 Time: 0735 5648 jurvy# 0992-Oil cet: N/A w perptio: Clearance ac1 work on lCS-3 Seyo:: A. Tech y B. Bossmann No enttv reqtired ino letdown HIX ro .moshieldiaddd for job # dptn/lOOeri( Locani>t 2 v.1K 3 6K flocr by rairi) 4 lOOK 5 1K i1r unde va1;:s)

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Appendix C Job Performance Measure Form ES-C-i

       -
                                               -  Wrksht              -

Facility: Shearon Harris Task No.: 301 005H401 Task Title: Determine Rod Misalignment Using JPM No.: 2011 NRC JPM Thermocouples and Evaluate Tech SRO Al-i Specs K/A

Reference:

G2.17 4.4 /4.7 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: The plant was at 90 percent power, with a load decrease in progress, when the CRS noticed that the DRPI indication for rod H02 was reading 24 steps higher than the group demand. The load decrease has been stopped and AOP-OOi entered. Initiating Cue: The CRS has directed you to calculate the temperature difference between thermocouple(s) adjacent to the misaligned rod and the average of symmetric thermocouple(s), using Attachment 2 of AOP-001 and the provided T/C Core Maps. 2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Job Performance Measure Form ES-C-i

 .
        -                                    WQrksht Task Standard:      All calculations within +/- 2° of actual.

Required Materials: Calculator General

References:

AOP-0O1, Attachment 1 and Attachment 2, Rev. 35 and Tech Specs Handouts: JPM Cue Sheets Pages 10-11 AQP-001, Attachments 1 and 2, (Rev. 35) Time Critical Task: No Validation Time: 16 minutes Critical Task Justification If the wrong thermocouples are used then none of the results will be Step 2 correct If the wrong values are selected then none of the results will be correct Step 3 If the calculation for the averages were incorrect the results will be Step 4 incorrect If the differences are calculated incorrectly then the candidate will come Step 5 to the wrong conclusion for Tech Specs If the wrong Tech Spec Action is selected an LCO action could be St ep 6 exceeded 2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 3 of 17 Form ES-C-i P-ERFORMANCE 1NFORMATIOF4 - - Start Time: Performance Step: 1 OBTAIN PROCEDURE (provided with handout) Standard: Obtains AOP-0O1 and refers to Attachments 1 and 2. Comment: Performance Step: 2 DETERMINE THERMOCOUPLE LOCATION(S) ADJACENT TO THE MISALIGNED ROD USING THE CORE GRID MAP (SHEET 1), AND CIRCLE LOCATION(S) IN TABLE ABOVE. THESE THERMOCOUPLES(S) ARE AFFECTED. Standard: Using the core grid map (Attachment 2, page 1 of 2), Determines affected thermocouples to be G02, J02, and H03. Circles G02, J02, and H03 on the table (Attachment 2, page 2 of 2). Comment: V Performance Step: 3 RECORD VALUES FOR ALL OPERABLE AFFECTED AND SYMMETRIC THERMOCOUPLES USING THE RVLIS CONSOLE OR ERFIS. SYMMETRIC THERMOCOUPLES ARE THOSE IN THE SAME ROW. Standard: Locates RVLIS Console and accesses T/C CORE MAP for Train A and Train B. (Printout of RVLIS core map provided in handout) Records value for Affected TC G02 (652°F) and Symmetric TC P07 (636°F). Records value for Affected TC J02 (652°F) and Symmetric TC P07 (636° F). Records value for Affected TC H03 (649°F) and Symmetric TCs C08 (636°F), H13 (640°F), and N08 (644°F). Corn ment: V - Denotes a Critical Step 2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 4 of 17 Form ES-C-i

                    -           PERFORMANGE lNFORMATIOF4                           -

V Performance Step: 4 DETERMINE THE AVERAGE OF SYMMETRIC THERMO COUPLES, FOR EACH AFFECTED THERMOCOUPLE. Standard: Determines (636°F) for G02s Symmetric TC Determines (640° F +/- 2°F) for H03s Symmetric TC Determines (636°F) for J02s Symmetric TC Comment: If the candidate includes the adjacent TCs with the EXAMINERS NOTE: Symmetric TC numbers the averages will be wrong and the end result will be that a wrong final difference will be given: Determines (644°F) for G02s Symmetric TCs Determines (640°F) for H03s Symmetric TCs. Determines (644°F) for J02s Symmetric TCs. V - Denotes a Critical Step 2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 5 of 17 Form ES-C-i

                       -*      PERFORMANCE INFORMATION v   Performance Step: 5   CALCULATE THE DIFFERENCE BETWEEN EACH AFFECTED THERMOCOUPLE AND THE AVERAGE OF ITS SYMMETRIC THERMOCOUPLES.

Standard: Calculates difference of 16°F 16°F for TC G02 9°F for TC H03 16°F forTCJO2 (+/- 2°F between all affected TCs and their symmetric TCs.) Reports that temperature difference is greater than 10°F. Evaluator Cue: CRS acknowledges calculations and report. (IF calculation difference is >10°F then) Cue: Evaluate Tech Specs for compliance. When evaluating Tech Spec compliance, assume that rod H02 is untrippable. Comment: EXAMINERS NOTE: If the candidate included the adjacent TCs with the Symmetric TC numbers the averages would have been wrong and the calculated difference would be 8°F. The report would be that the temperature difference is less than 10°F. This report would provide the CRS with inaccurate information. V Denotes a Critical Step

  -                                              2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 6 of 17 Form ES-C-i

                           . PERFORMANCE INFORMATICN v   Performance Step: 6  OBTAIN AND EVALUATE TECH SPECS Standard:            Obtains Tech Specs and refers to LCO 3.1.3.1 Determines that ACTION a. is applicable. (See Attached)

(IF candidate incorrectly calculated the temperature difference the Tech Spec reported will be 3.1.3.2 ACTION a) Evaluator Cue: CRS acknowledges Tech Spec call. ENDOFJPM Comment: Stop Time: V Denotes a Critical Step

  -                                           2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 7 of 17 Form ES-C-i

            ...                       PERFQRMANcNFQf{MAT[ON                                    -

KEY I MAISUNCTION OF ROD CONTROL AND INDICATION SYSTEM I Attachment 2 Adjtcent and Symmetric Thermocouple Locations

.-.

Sheet 1 of 3 THERMOCOUPLE LOCATIONS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A i - -- - -- iI I i I B ft *

I I

I - - - I I C H ft r 7 I I - - - - 0 T ft ft ft ft E ,. T ft T T T w T 7 F ft T ft ft ft 7 ft T ft T ft r ft 7 ft G ft 7

-.

H T ft T ft 7 R T V R K ft T ft ft ftT ft R L ft T ft 1 ft v M T ft ft 7 ft 7 ft N T ft 7 ft 7 ft T P ft 7 ftT ft R T R Control Rod

T Thermocouple

T- Thermocouples abandoned by EC 4797 AOP-O0I Rev. 2.5 Page 41 of 47 V - Denotes a Critical Step 2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 8 of 17 Form ES-C-i

                                    - PERFORMANCE INFORMATION-                     -

KEY I MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM Attachment 2 Adjacent and Symmetric Thermocouple Locations

Sheet 2 of 3 NOTE iO. E07, H08. K08, and POB have no symmetric Iocations.

               . Symmetric thermocouples are those in the same row.

SYMMETRIC LOCAI9ONS GRID I______ LV TRAIN A B A B A B A B AO8 H15 GO1* G15 R07 S I B05 E14 L14* Y 0 CCC H13 NOB HG3) M C D03 C12 N04 M02 lvi A EC4 D05 E12 Mu L12 E T Hil ECS L08 H05 T I F05 Fil Elo K1I* K05 L06 R 0 FC3 F13 NW NOS K03 I N GOB F09 J1O C S G08 H09 (G02) (Jo2 P07 M09 J12 Themiocou pies abandoned by EC 47997

1. DETERMINE thermocouple location(s) adjacent to the misafgned rod using core grid map iSheet I\ AND CIRCLE location(s) in Table above AOP-OO1 Rev. 35 Page 42 of 47 V - Denotes a Critical Step 2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 9 of 17 Form ES-C-i

        -
                           -         PERFORMANCE INFORMATION                -

KEY TIC CORE MAP (DATA SHEET 1) TRAIN B MSG # 245 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A A B 632 B C C D 1636 650 E I 644 50 640 6321 E F 1 50 644 I F G ISO 644 6G HI 644 IH 640 50 K I 640 I K L I 644 640 644 50 L M 1636 I M N I 640 N P P 8 R 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 TRAIN A TIC CORE MAP MSG # 245 1 2 3 4 12 13 14 15 A 50 A B 636 B C 632 C D D E 636 640 E F 644 648 644 F G 640 G H 640 644 652 H J J K 640 644 50 K L L M 640 644 M N P 636 640

                                             ©640 N

P R 636 R 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 V - Denotes a Critical Step 2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 10 of 17 Form ES-C-i

PERFORMANCE INFORMATIOI4 KEY I MALFUNCTION Of ROD CONTROL AND INDICATION SYSTEM Attachment 2 Adjacent and Symmetric Thermocouple Locations

Sheet 3 of 3

2. RECORD the following in the table below:

Adjacent TC number
Adjacent TC value using the RVLIS Console, ERFIS, or OSI-Pi
Symmetric TC nunibeis (not including adjacent TCs)
Symmetric TC values for all OPERABLE TCs using the RVLIS Consoler ERF1S, or OSI-PI

3. DETERMINE the average of .smmetric thermocouples, for each adjacent thermocouple.

Adjacent TC Symmetric TC Symmetric TC Number Value Number Value Average J02 N/A P07 G36 G02 652 Q.9 636 H13 640

                 !O                                  N05              644          G40 C02            N/A P07             636 J02                652                                            636

4. COMPARE each adjacent thermocouple value hsted to its symmetric thermocouple average for indication of a misaligned rod (REFER TO Attachment 1.)

                                        --END OF ATTACHMENT 2--

AOP-OCI 1 I Rev. 35 Pa!Je 43 of 47 V Denotes a Critical Step

 -                                                           2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 11 of 17 Form ES-C-i

    .
                                 -      PRFQ.RMANC [NFORMATIO4                                -    V KEY 3/0.1 .3  1OvABLE CDTROL ASSEL IS RIlP HlE(iHT L1Mifl43 CDOITtOl FOR OPERATION 31 .3.1 All shutdon end control rods shall be OPERABLE and positioned within
         +/- 12 steps cm       cued position) of thr group step coiitr fliit pQsit1On APPLICBILttY:        HOLIE5 1 end 2,
                . With one or #nore rods inoperable due to being isinoveble       as a result of excessive friction or echantcai interference          or krawn to be untrippable, determine that the SHUTCQN MP.G1N             ulrerienl of Specification 3i.l..1 is satisfied withn 1 hour d            Oc n HOT STANh1 withn 6 hours.

b. With more tFan one rod ?nis&igned frcn the group stop counter deirand position by nore than +/- 12 steps (indicated position), be in HOT STAflCY within 6 hours.

c. With more then one rod inoperable, due to a rod control urgent falure alarm or obvious eIectrlcai proolew ifl the rod control syst e.xistinq ftc greater than 36 hours, be in HOT SiAtiI3Y within the following 6 hours.

d. With one rod tnippable but inoperable due to causes other then addressed by ACTION a.. above, or nisaligned froii its group step counter deniend height by nore than +/- 12 steps indicated position), PER OPERAJION may continue provided that within hour:

1 The rod is restored to OPER3LE status within the above alignment requirements. or

2. The rod is declared inoperable and the reniai nder of the rods in the group with the inoperable rod are aligned to within

                               +/- 12 stops of the inoperable rod while maintaining ihe rod sequence end insertion limits of Sped fi ceton 3.1.3 6.         Th ThERMAL POWER lewel shel I be restricted pursuant to Specification 3.1.3.6 during subsequent  operation.. or

3. The rod s declared inoperable end the 5HUTOO MARGIN reauireweet of Soecifiction 3.1.1.1 is satisfied, P(JE.R OPERATION cay then continue provided that

                               )      A reevaluation of each accdemt analysis of Table 3.1.1 1 performed ith1n 5 days: this reevaluation shell confirm that the previously analyzed results of these accicents See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

SHEAN HARRIS - UNIT 1 3/4 114 .Asieridrnent Wn, 25 V - Denotes a Critical Step 2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 12 of 17 Form ES-C-i

            -
                             ..*     PERFORMANCE INFORMATION                                   - -

KEY [ICACI iVltYjNThiLyZEj UNITING CCINDON FOil OPERATTc:N ACTION (Cant muse): remain vol id for the duration of operation under these conditions dl The SF4UTDDWIE MR6IN requirement of Specticoton 3.1 1.1 is determined at least once per 12 tours: c) A pcter distribution map is obtained from the riovabie incore detectors and F (Z) and 0 F? are verified to be within their limits within 72 hours: and dl The ThERMAl POWER level is reduced to Than or equal to 15 of RATED rwERt4At POWER within the next hour and within the following 4 bciurs the Hiqai Neutron Flux Trp Setpe?nt is reduced to less than or equal to as of RATED lKERttAL POWER. SURVL ILLANCE REQUIREMENTS 4.1.3. 1.1 The posit ion of each rod shal 1 be detontsned to Lie within the group demand limit by verifying the individual rod positions at least once per 12 hours exceot during tri intervals sthen tho rod posttion do-viauon rmtriitor is inoperable, then yen fy the group positions at least once per 4 hours. 41.312 Each rod em rully inserted in the core shall be determined to be OPERABLE by movoment of at least 10 steps im any one dlrectlon at least oneb per 2 days. rgr\p ItAPP P ONIT I : I II oerR1rwot to. V Denotes a Critical Step

 -                                                        2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 13 of 17 Form ES-C-i

..

PERFQRMANC1itFQRMAT1QN KEY TaLE 311 ACC tWt A$ALYS5 REOUtRt?G REVM..UAflON pi Rc Cluster Control ssembty tsertion Caracterivts Rod Clstar Control Ass eobly 1 sal1ent Loss 4f Reactor Coolant froa Siiall Ruptured Pi,s or frc Cracks n Large Pipes htch tiatas t. Erency Cire Cool hig 5ysta Sinqia od Ciurtar Control Assal W1trmal at Full Pow ajar Reaetor Coolant Sys ps uturs (LsofCoalnt Acci dafit) aor Sac ndar7 Coolant Stst Pipa Ruptur, uture of a Contrl Rod Ortv Mechanise Kou*1rg (Rod Cluster Controt Asei1 eethin) HURO4 ARR!S Lillfl 3. 3/4 6 V - Denotes a Critical Step 2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 14 of 17 Form ES-C-i

PERFORMANCE INFORMATION KEY EActtvrrv CN1ROL SVSTE4S POtflON NOtCATt SVSTENS OPRATtNG I U4itING CONOITtON QR OPERAflN 3.t.3.2 the Diçital Ro4 sftion tndication System and the Demand sition Indication System shall be OPERABLE and capable 01 d.terslnfng the shutdwn and control rod positions within t U steps, APPucAsrLrrf 14ODES 1 and 1. ACTTQN:

a. With a azinu of one digital rod position indicator per bank inoperable either:

1. D.tarisfn. thi position of th noniridicatlng rod(s) Indirectly by the ecva T. I ncore 4atactori at I east once per 8 hours and inmediately after any notion of the nonfndtcatinq rOd which exceeds 24 stIps In one direction since the last eterninatIon of the rOd position, or

2. Reduce ThERMAL POWER to less elan S of RATED ThERMAL POWER with4 a hcri.

b. With a m*xi*a of one demand position Indtcatrn per tank inoperable either:

1. VerIfy that all digital rod pCsltion indicators fr the affct.4 bank are QPEAe1.Lati that 4 wi tJldliim rod and the least wtthdrn rod of the bank ar.-iith1n a is of 32 *t*ps of udi other at l.t once per S sri, or

2. Reduce TNERkAL. POWER to 1*si than 5 oi RATED ThE$AL POWER within a hours, SURVEtLLMCE REQjtRENTS 4.1.3.1 Each dfital rod position Indicator shall be determined to be QPERAaL,E by veT! fying that the Demand Position Indication Syst and the Digital Rod Pos1tIn Indication System agree within 12 steps at. least once per 12 hours exc*t during t1e Intervals when the rod position deviation monitor is Inoperable, than coar. the Ceand Position Indication System and the Digital Rod Position Indication System at lust once par 4 hours.

I 5iEAROH 4AaRS - UNIT 1 3/4 1-12 V Denotes a Critical Step

 -                                                      2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 15 of 17 Form ES-C-i VER[F[CATlO OF COMPLETION Job Performance Measure No.: 2011 NRC JPM SRO Al-i DETERMINE ROD MISALIGNMENT USING THERMOCOUPLES Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: 2011 NRC Admin Exam SRO Al-i Rev. 1

Appendix C Page 16 of 17 Form ES-C-i

                   ,              JPMCUESHEET                        -

Initial Conditions: The plant was at 90 percent power, with a load decrease in progress, when the CRS noticed that the DRPI indication for rod H02 was reading 24 steps higher than the group demand. The load decrease has been stopped and AOP-OO1 entered. Initiating Cue: The CRS has directed you to calculate the temperature difference between thermocouple(s) adjacent to the misaligned rod and the average of symmetric thermocouple(s), using Attachment 2 of AOP-001 and the provided T/C Core Maps. 2011 NRCAdmin Exam SROA1-i Rev.1

Appendix C Page 17 of 17 Form ES-C-i

JPMCLJESI-IEET- - - TIC CORE MAP (DATA SHEET 1) TRAIN B MSG #245 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A I 1 A B I 632 I B C I 636 1 C 0 1636 650 I____ E 644 50 640 632 1 E F 50 644 F G 150 644 632 H I 649 644 IH J 640 50 K I 640 K L 644 640 644 50 L 1 M 1636 I N 640 N I 636 P R R 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 TRAIN A TIC CORE MAP MSG #245 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A I 50 A B 1636 I B C I 632 C I E I 636 640 E F 644 648 644 F G I 652 640 H I 640 644 652 640 640 I H I 652 K I 640 644 50 I K L I M 1 640 644 I M N I 636 640 644 N P I 640 I P R I 636 R 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 2011 NRCAdminExamSROAl-1 Rev.1

Appendix C Page 1 of 1 1 Form ES-C-i WORKSHEET [NFQRMA-TlQr$ - - Facility: Shearon Harris Task No.: 301 1 35H601 Task Title: Determine Subcoolinp with the JPM No.: 201 1 NRC Exam Subcoolinp Marciin Monitor Admin JPM SRO Ai-2 Unavailable K/A

Reference:

G 2.1.23 RO 4.3 SRO 4.4 Alternate path: No Examinee: NRC Examiner: Facility Evaluator: Date: Method of testinQ: 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:

A LOCA has occurred
SI is actuated
PATH-i is in progress
Containment pressure is 3.3 psg
All RCPs are running
The Subcooling Margin Monitor is not available
The hottest CET is reading 565°F
ERFIS Pt. TRC9300 is not available
Loop Thots are reading as follows:

Tl-413 = 559°F Tl-423 = 558°F Tl-433 = 557°F

All Loop Tavg are reading 557°F
ERFIS Point PRC9455L has failed
Pressurizer Pressure Channels are reading as follows:

P1-457 = 1740 psig P1-456 = 1730 psig P1-455 = 1 73spsig

RCS Wide Range Pressure Channels are reading as follows:

P1-402 = 1690 psig P1-403 = 1695 psig The CRS has directed you to determine and report the Subcooling ni ia ti ng C ue. margin.

2011 NRC Admin Exam JPM SRO Ai-2 Rev. 1

Appendix C Page 2 of ii Form ES-C-i . WORKSKEET INFQRMATION 2011 NRC Admin Exam JPM SRO A1-2 Rev. 1

Appendix C Page 3 of 1 1 Form ES-C-i

        .                        WOEKSHEET [NEQRMAT[QN          -

Task Standard: Correct indications utilized and Subcooling margin determined within specified range. Required Materials:

Calculator
Steam Tables General

References:

EOP USERS GUIDE Rev. 30 Handouts:

EOP USERS GUIDE, Table of Contents
EOP USERS GUIDE, Section 6.2 (pgs. 33 and 34)

Time Critical Task: No Validation Time: 12 minutes Critical Task Justification Step 2 Must choose correct temperature to use based on provided plant conditions. IF the wrong temperature is selected all calculations will be incorrect. Step 3 IF Containment pressure is not identified as ADVERSE then all calculations will be using the normal Containment values and the calculations will be incorrect. Step 4 IF the saturation temperature were incorrectly calculated the final calculation will be incorrect. Step 5 Final Subcooling calculation is what the candidates task was. If the reported values are incorrect the CRS may make incorrect choices with procedure steps based on the value given. 2011 NRC Admin Exam JPM SRO Ai-2 Rev. 1

Appendix C Page 4 of 1 1 Form ES-C-i

     .                 -      PERFORMANCE ILFQRMAT1ON Start Time:

Performance Step: 1 Refers to EOP Users Guide. Comment: The candidate is not required to complete the task in discrete steps. Guidance for performing the task is provided in the EOP USERs GUIDE but procedure steps are not specified. The specified parameters must be selected for the subcooling calculation to be correct. q Performance Step: 2 Evaluate plant conditions:

RCS temperature Standard: Determines the hottest CET reading is the preference and chooses:
565°F Comment:

q Performance Step: 3 Evaluate plant conditions:

RCS Pressure Standard: Determines containment conditions are adverse:
Pl-402=169OPSIG Comment:

2011 NRC Admin Exam JPM SRO Al -2 Rev. 1

Appendix C Page 5 of 1 1 Form ES-C-i

                        -  PERFORMANCE iNFORMATION q Performance Step: 4 Determine saturation temperature.

Standard: Convert to PSIA: 1690 + 15 = 1705 PSIA Interpolates between 1700 and 1740 PSIA and determines saturation temperature to be 61 3°F but 61 4°F:

                          * [5/40(616.385 61 3.189)] = 0.4
                                           -

613.189+0.4=613.6°F

                          * >613614 Comment:           Candidate can use the Steam Tables.

q Performance Step: 5 Determine subcooling. Standard: Calculates and reports subcooling to be 48°F but 49°F

613.5°F-565°F= 48.5°F Comment:

Terminating Cue: After the candidate has reported the calculated Subcooling margin: Evaluation on this JPM is complete. Stop Time: 2011 NRC Admin Exam JPM SRO Al -2 Rev. 1

Appendix C Page 6 of 11 Form ES-C-i

          -                  VERLF[CATIQN OF COMPLETION Job Performance Measure No.:  2011 NRC Admin Exam JPM SRQ A1-2 Determine Subcooling with the Subcooling Margin Monitor Unavailable Examinees Name:

Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: 2011 NRC Admin Exam JPM SRO Al -2 Rev. 1

Appendix C Page 7 of 1 1 Form ES-C-i JPMCUE SHEET RETURN TO EXAMINER WHEN COMPLETED INITIAL CONDITIONS:

A Small Break LOCA has occurred
SI is actuated

                        . PATH-i is in progress

Containment pressure is 3.3 PSIG
All RCPs are running
The Subcoollng Margin Monitor is not available

                        . The hottest CET is reading 565°F
                        . ERFIS Pt. TRC9300 is not available

Loop Thots are reading as follows:

Tl-4i3 = 559°F TI-423 = 558°F Tl-433 = 557°F

All Loop Tavg are reading 557°F.
ERFIS Point PRC9455L has failed
Pressurizer Pressure Channels are reading as follows:

P1-457 1740 psig P1-456 = 1730 psig P1-455 = 1735 psig

RCS Wide Range Pressure Channels are reading as follows:

P1-402 = 1690 psig P1-403 = 1695 psig TheCRS has directed you to determine and report the Subcooling INITIATING CUE: NAME DATE Subcooling margin = °F 2011 NRC Admin Exam JPM SRO A1-2 Rev. 1

Appendix C Page 8 of 1 1 Form ES-C-i JPM CUE SHEET - - Progress Energy lnfornation HARRIS NUCLEAR PLANT PLANT OPERATING MANUAL VOLUME 3 PART 4 PROCEDURE TYPE: EMERGENCY OPERATING PROCEDURE (EOP) NUMBER: EOP-USERS GUIDE TITLE: USERS GUIDE j EOPUSERS GUIDE Rev. 30: I Page 1 of 69 2011 NRC Admin Exam JPM SRO A1-2 Rev. 1

Appendix C Page 9 of 11 Form ES-C-i

                                            -   .      JRMCUESHEET GUIDE USERS Table of Contents Section 1.0   Purpose                                                          4 2.0   References                                                       5 3.0   Responsibilities                                                 8 4.0   Definitions/Abbreviations                                        9 5.0   Procedure                                                      10 5.1 Control Room Usage of the EOP Network                        10 5.2 Control Room Usage of Status Trees                           19 5.3 Control Room Usage of EPPs, Fokiouts, arid FRPs              24 6.0 General Information                                              33 6.1 Background and Basis for EOP Network                         33 6.2 RCS Subcooling                                                33 6.3 Resetting SI. Phase A, Phase B and FW isolation              35 6.4 Sequencer Operation                                          35 6.5 Stable Pressure/Temperature                                  35 6.6 Realignment of Plant Equipment Following SI Termination                                    36 6.7 Definitions of Verify, Check andActuate                 36 6.8 Use of RCS Wide Range Pressure Indication                     38 6.9 Dump Steam at Maximum Rate                                   38 6.10 Control of Ruptured Steam Generator Level                    39 6.11 Use of NORMAL
                      -                                                  40 6.12 PATh GUIDES                                                 40 6.13 Use of Operating Procedures                                  41 6.14 Plant Instrumentation and Plant Computer                     42 6.15 Use of PRZ Spray During RCS Depressunzation                  43 6.16 Use of Charging to Control RCS Inventory                     44 6.17 SI Reinitiation                                              45 6.18 TDAFW Pump Speed Controller Setpoint                        45 6.19 Tech Spec coolclown and Pressure/Temperature limits    .. 46 6.21) Determining RCS Temperature and Cooldown Rate              46 6.21 Using Core Exit TCs to determine Inadequate Core Cooling Conditions                                          47 6.22 Consulting the Plant Operations Stall                        47 6.23 Shutdown Margin Evaluation                                   48 6.24 CSIP Alternate Miniflow Valves                               48 6.25 Safeguards Verification During FRP Implementation   .... 50 6.26 Restoration of RCP Cooling and RCP Restart                  50 6.27 Use of BANK SELEC During an A1WS                            52 6.28 RCP Restart Following a SGTR                                 52 6.29 Loss of SI Flow Indication                                  53 6.31) Contingencies for Termination of SI Flow                   54 6.31 Torque Switch and Overload Protection                       54 6.32 Conservation of the 250 Volt Station Battery                55 6.33 Potential Gas Intrusion Into the CSIP Suctions              57 6.34 Transition to Severe Accident Management Guidance..    .  . 58 6.35 Immediate Actions During an ATWS                            59 EOP-USERS GUIDE                     I             Rev. 30                 I     Page 2 of 69 2011 NRC Admin Exam JPM SRO Al -2 Rev. 1

Appendix C Page 10 of ii Form ES-C-i JPMCUE SHEET - - -. GUiDE USERS 60 GENERAL INFORMATION 61 Background and Basis for EOP Network During the verification and validation of the EOP network, and during Operator simulator training, many questions are frequently asked concerning the EOP networic The background and basis Itir the SHNPP EOP network is found in detail in the background documents of the WOG ERGs and the EOP Step Deviation Documents The following sections contain clarification of certain procedural requirements that are frequently questioned by the operators.

    &2 RCS Subcooling The ERFIS plant computer functions as the plant subcooling monitor. RCS subcooling will normally be obtained from the top level Safety Parameter Display System (SPDS) screen (Turn-on-code:

SPTOP, Parameter SUBCOOL {DEGFy, ERFIS point TRC9400). If for some reason the subcooling monitor is not available, the operators will manually determine subcooling using one of the following (Reference 2222): a Graph provided on the CSFSTs

Subcooling Margin Caic. Program Version 1.0

Steam Tables Subcooiing values are generally presented in the following format 1 O F 140 F] C-2LP F (50 F] M-The top set of values is normally used when the subcooling monitor is available (designated by C). The bottom set of numbers is used only when the subcooling monitor is not available (designated byM for manual). The subcooling values used in the procedure were determined based on specific instrument inaccuracies. Should it be necessary to manually determine subcooiing, the following conventions apply:

1. Primary temperature is obtained using one of the following based on availability of the indications (listed in order of preference):

a Core exit TC reading on SPDS (Turn-on-code: SPTOP, Parameter T EXIT (OEGF), ERFIS point: TRC9300). This reading is the average of the live hottest core exit TCs and is the input used for the Subcooling Monitor a Highest core exit TC reading from the inadequate Core Cooling Monitor (IGCM).6.2 RCS Subcooling (continued) EQP-USERS GUIDE I Rev. 30 I Page 33 of 69 2011 NRC Admin Exam JPM SRO A1-2 Rev. 1

Appendix C Page ii of ii Form ES-C-i JPM CUE SHEET - - .. - GUIDE USERS Highest active loop wide range T-hot (Tl-413. 423, 433). An active loop is defined as one that has forced or natural circulation flow. It any RCPs are running, all loops will be active (backtlow is available in loops where RCPs are not running). A classic example of a non-active loop would be a loop that has a SGTR since it is isolated and natural circulation flow in this loop would not be available.

2. Primary pressure is obtained using one of the following based on the range and availability of RCS and PRZ pressure indication:

If ERFIS is available, then use the RCS pressure reading on SPDS (Turn-on-code: SPTOP, Parameter: PRZ PRES (PSIGy, ERRS point PRC94SSL). If PRZ pressure is above 1700 PSIG, this reading is the lowest of the three PRZ pressure channels (PT-457, PT-456, and PT-455). IF PRZ pressure is below 1700 PSIG, this reading is the lowest of the two RCS wide range pressure channels: PT-402 (ERFIS point PRCO4O2) and PT-403 (ERFIS point PRCO4O3).

If PRZ pressure is greater than 1700 PSIG and CNMT conditions are normal, then use the lowest PRZ pressure indication (P1-457. P1-456, or P1-455.1).
If PRZ pressure is oft scale low or adverse CNMT conditions exist, then use the lowest of the two RCS wide-range pressure indications P1-402.1 or P1-403.

Only PT-402 and PT-403 are used since these transmitters are located outside containment

When RCS pressure is less than 700 PSIG, Pl-402A should be used. Pl-402A receives input from qualified instrument PT-402 and its narrow range scale provides a mare precise indication of pressure.

EOP-USERS GUIDE I Rev. 30 I Page 34 of 69 2011 NRC Admin Exam JPM SRO Al -2 Rev. 1

Appendix C Page 1 of 6 Form ES-C-i PERFORMANCE INFORMATION Facility: Shearon-Harris Task No.: 002001 H201 Task Title: Review (for approval) a completed JPM No.: 2011 NRC Admin surveillance procedure for PORV SRO JPM A2 block valves. K/A

Reference:

G2.2.12 (3.4) Examinee: NRC Examiner: Facility Evaluator: Date: Method of testincj: 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:

The unit is operating at 100% power.
PRZ PORV PCV-445B has a failure in the SHUT circuit. RC-1 15 has been closed and power is removed. TS 3.4.4 Action b is in effect. EIR 20110285
The control room crew has completed OST-1017, PRESSURIZER PORV BLOCK VALVE FULL STROKE TEST QUARTERLY INTERVAL MODES 1-2-3-4.

Initiating Cue: You are the CRS. Review the completed OST for approval. 2011 NRC Admin Exam JPM SRO A2 Rev. 1

Appendix C Page 2 of 6 Form ES-C-i PERFQRMAE [NRMAON Task Standard: All errors identified. Required Materials: None General

References:

OST-1017, PRESSURIZER PORV BLOCK VALVE FULL STROKE TEST QUARTERLY INTERVAL MODES 1-2-3-4, Revision 21 Handout: Completed OST-1 017 with errors that align with the JPM content. Time Critical Task: No Validation Time: 15 Minutes Critical Task Justification Identification of stopwatch beyond calibration date all timing data It e m collected with out of cal device is non usable therefore the test is invalid. Missing initial and date for step marked N/A. lAW PRO-NGGC-0200 Section 9.2.26.a.2) If the section or step is N/Nd the respective work group supervisor shall initial/date and document justification unless this It e m 2 is allowed by the implementing procedure. In the case of the step that was N/Ad it is not allowed by the procedure and therefore should have been initialed and dated. Shut time for 1 RC-113 exceeding limit if not identified an inoperable

Item 3 component could be relied upon and fail when needed to perform its intended action. 2011 NRC Admin Exam JPM SRO A2 Rev. 1

Appendix C Page 3 of 6 Form ES-C-i PERFORMANCE INFORMATiON START TIME: Performance Step: 1 Obtain procedure. Standard: Reviews Sections 3.0, 4.0, 5.0, 6.0. Evaluator Cue: Provide handout for AUDIT JPM SRO A2. Evaluator Note:

The steps of reviewing the procedure can be completed in any order.
There are three errors in the procedure. Only the errors are documented in the JPM.

Comment: Performance Step: 2 Review the completed OST-10i7. V Standard: Identifies Stopwatch beyond calibration date per Prerequisite

3.0.4. Comment

Performance Step: 3 Review the completed OST-1017. V Standard: OST-i 017 Page 9, N/A for 1 RC-i 15 with comment 1 was not initialed and dated per PRO-NGGC-0200 Section 9.2.26.a.2). Comment: V Denotes Critical Steps

 -                                          2011 NRC Admin Exam JPM SRO A2 Rev. 1

Appendix C Page 4 of 6 Form ES-C-i PERFORMANCE iTFORMAT1ON Performance Step: 4 Review the completed OST-i 017. Standard: SHUT time for 1 RC-i 13 exceeds LIMITING VALUE. Comment: Terminating Cue: STOP TIME: V Denotes Critical Steps

 -                                        2011 NRC Admin Exam JPM SRO A2 Rev. 1

Appendix C Page 5 of 6 Form ESC-1 VERIFICATiON OF COMPLETION Job Performance Measure No.: 2011 NRC Admin SRO JPM A2 Review (for approval) a completed surveillance procedure for PORV block valves. OST-1017 Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: 2011 NRC Admin Exam JPM SRO A2 Rev. 1

____ Appendix C Page 6 of 6 Form ES-C-i JPM CUE SI-rEET INITIAL CONDITIONS:

The unit is operating at 100% power.
PRZ PORV PCV-445B has a failure in the SHUT circuit. RC 115 has been closed and power is removed. TS 3.4.4 Action b is in effect. EIR 20110285
The control room crew has completed OST-1017, PRESSURIZER PORV BLOCK VALVE FULL STROKE TEST QUARTERLY INTERVAL MODES 1-2-3-4.

INITIATING CUE: You are the CRS. Review the completed OST for approval. NAME DATE IF any discrepancies were identified in the review of OST-1 017 list them on the lines below 2011 NRC Admin Exam JPM SRO A2 Rev. 1

Appendix C Job Performance Measure Form ES-C-i

Worksht - - - - Facility: Shearon Harris Task No.: 345001 H602 Task Title: Classify an event JPM No.: 2011 NRC Exam Admin JPM SRO A4 K/A

Reference:

G2.4.41 RO 2.9 SRO 4.6 Examinee: NRC Examiner Facility Evaluator: Date: Method of testinci: 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: A Reactor trip and Safety Injection have just occurred from 100% power due to low steamline pressure. Initiating Cue: Using the attached information sheet and the EAL Matrix, classify the event. Mark the EAL Matrix appropriately. THIS IS A TIME CRITICAL JPM. 2011 NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Job Pertormance Measure Form ES-C-i

                            .                Worksheet Task Standard:      Event classified as an Alert (HA2.i)

Required Materials: None General

References:

PEP-lb EAL Matrix EP-EAL (allowed reference) Handouts: JPM Cue Sheets Pages 7 and 8 PEP-lb EAL Matrix EP-EAL (allowed reference) Time Critical Task: Yes Validation Time: 15 minutes Critical Step Justification Step 2 Classification of the event is critical for determining State and County notifications, public information notices, site information notices, and event reportability to the Nuclear Regulatory Commission. 2011 NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Page 3 of 8 Form ES-C-i

                         .      PERFORMANCE INFQRMAT[ON Evaluator Note:        Start Time for this JPM begins when the individual has been briefed START TIME:

Performance Step: 1 OBTAIN EAL Matrix. Standard: Obtains EAL Matrix. (EP-EAL is an allowed reference) Comment: v Performance Step: 2 CLASSIFY EVENT Standard: Identifies an Alert due to Explosion in Table H.i area damaging Safe S/D equipment (HA2.i) Initiating Condition: Fire or explosion affecting the operability of plant safety systems required to establish or maintain safe shutdown HA2.1 Alert Fire or explosion resulting in EITHER: Visible damage (Note 4) to any Table H-i structure OR system/component required for safe shutdown of the plant OR Control Room indication of degraded performance of any safe shutdown structure, system, or component within any Table H-i area Comment: STOP TIME: Terminating Cue: Event classification stated to evaluator. ENDOFJPM V Denotes a Critical Step

  -                                             2011 NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Page 4 of 8 Form ES-C-i PERFORMANCE INFORMATION I Emergency Action Levels Attachment I Emergency Action Level Technical Bases Catory: H Hazards Subcategory: 2 Fire or Explosion Initiating Condition: Fire or explosion atfecting the operability of plant safety systems required to establish or maintain safe shti:tdown EAL: 14A2.1 AlGrt Fire or explosion resulting in EITHER: Visible damage (Note 4) to ny Table H1 structure OR system/component required for safe shutdown of the plant OR Control Room indication of degraded performance of any safe shutdown structure, system, or component within any Table H-I area N.te 4:: Visible Carnage ta:

Dm3e t uprnnt yr tjr ht i rdiy b ribi witht m ttrig, r mIy

                -    Damage is sufficiert to cause ccncern reganting the cntinued operabUity or redabtity of affected safety rc1ure.           r corn potnt Example damage includes: deformedon due to heat or impact, denting, penetration, rupture, cracking, paint bIistt1rg Vbe       amage dcs not inchide surface blemishes (eg., pamt chippin, scratches)

Table H-i Structures Containing Safe Shutctown Equipmest

Containment
Reactor Auxiliary Suilding
Fuel Handling uiding Waste Pcceasng Euilding
Illrbirte uiid irtg (irludirtg Trartsfrmr Araa)

Emergency Diesel Generator Suilding

Diese Fuel Oil to rage Buildrrg (DFOST)

ESW Intake Structure

Auxiliary Reservoir Intake Strctire
NSW -Structure Se.titchyard
Th rd 2 I Duct Sariks ( ndergrcund raceways conta rnng Safa Stutdv puwr, corttrd ard insbtirnettt cab[s) sMng any of tIie above areas Mode Applicability:

All EP-EAL Rev. S Pa9e 158 of 296 V - Denotes a Critical Step 2011 NRC Exam Admin JPM Sf0 A4 Rev. 1

Appendix C Page 5 of 8 Form ES-C-i PERFORMANCE INFORMATION Emergency Action Levels Attachment I Emergency Action Level Technical Bases

Basis: Genenc VISiBLE DAMAGE is used to identify the magnitude of the FIRE or EXPLOSION and to discriminate against minor FIRES and EXPLOSIONS. The reference to structures containing safety systems or components is included to discriminate against FIRES or EXPLOSIONS in areas having a low probability of affecting safe operation. The significance here is not that a safety system was degraded but the fact that the FIRE or EXPLOSION was farge enough to cause damage to these systems. The use of VISIBLE DAMAGE should not be interpreted as mandating a lengthy damage assessment prior to classification. The declaration of an Alert and the activation of the Technical Support Center will provide the SEC with the resources needed to perform detailed damage assessments. The SEC also needs to consider any security aspects of the EXPLOSION. Escalation of this emergency classification level, if appropriate, will be based on EALs in Category Sr Category F or Category R. Plant-Specific The Table H-I vital area structures were obtained from the l-{NP safe shutdown analysis (ref. 1). A steam ilne break or steam explosion that damages permanent structures or equipment would be classified under this EAL. The method of damage is not as important as the degradation of plant structures or equipment. The need to classify the steam line break itself is considered in fission product barrier degradation monitoring (EAL Category F). HNP Basis Reference(s): I, AOP-036, Safe Shutdown Following A Fire

2. FSAR 7.4 I EP-EAL Rev. 9 Page 159 of 296 V - Denotes a Critical Step 2011 NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Page 6 of 8 Form ES-C-i

                            . VERIFICATIOr\1 OF COMPLETION Job Performance Measure No.:    2011 NRC Exam Admin JPM SRO A4 Classify an event
                                                               -

Examinees Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: 2011 NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Page 7 of 8 Form ES-C-i

                   .              JPMCUESHEET Initial Conditions:   A Reactor trip and Safety Injection have just occurred from 100% power due to low steamline pressure.

Initiating Cue: Using the attached information sheet and the EAL Matrix, classify the event. Mark the EAL Flow Path appropriately. THIS IS A TIME CRITICAL JPM 2011 NRC Exam Admin JPM SRO A4 Rev. 1

Appendix C Page 8 of 8 Form ES-C-i JPMCUESHEET CLASSIFICATION INFORMATION SHEET A Reactor trip and Safety Injection have occurred due to low steamline pressure B Train has lost off-site power On start, the 1 B-SB EDG experienced a crankcase explosion resulting in diesel engine damage and damage in the engine room 1 B-SB bus remains de-energized Steam Generator Pressures are:

A SG 900 psig
B SG 350 psig and lowering
C SG 900 psig The Turbine Driven AFW pump has started and tripped on overspeed Containment pressure has reached ii PSIG and is slowly increasing The A-SA Containment Spray Pump started and tripped on overcurrent All radiation monitor readings are normal CSFSTs:
Heat Sink is YELLOW
Inventory is YELLOW
All other CSFSTs are green Classify the event Name Date:

Record your classification here and return to the examiner. EAL Classification: 2011 NRC Exam Admin JPM SRO A4 Rev. 1}}

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