ML081840494

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Retake Exam 05000338-06-302 Draft Job Performance Measures (Part 1 of 2)
ML081840494
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 07/02/2008
From:
- No Known Affiliation
To:
NRC/RGN-II
References
Download: ML081840494 (63)
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Text

1.

2.

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5.

Draft Submittal (Pink Paper)

Norz-11-1 AJJtV A 2 oCG ** 3 02-12<=- TA (C e Ru CU[L,netJ

.:) KO AbMIAJ.

Administrative Topics Outline (ES-301-1) vi Control Room Systems & Fapility Walk-Through Test Outline (ES-301-2)

Iv}A Administrative JPMs/

In-plant JPMs ~ vJ}A.

Control Room JPMs (simulator JPMs) _ Nj~

ES-301, Rev. 9 DRAFT Administrative Topics Outline Form ES-301-1 Facility: North Anna Power Station Date of Examination:

Examination Level (circle one):

SRO Operating Test Number:

1 Administrative Topic (see Type Describe activity to be performed Note)

Code*

KA N,CLR 1-PT-23, QUADRANT POWER TILT RATIO Conductof Operations 015-A1.04 DETERMINATION Review for completeness (faulted)

(3.5/3.7)

M,CLR 1-FP-1.3, RESPONSE TO VOIDS IN REACTOR VESSEL Conductof Operations GEN 2.1.25 Calculate head vent time (2.8/3.1)

M,CLR 1-GOP-13.0 ALTERNATE CORE COOLING METHOD Equipment Control 005-A1.06 ASSESSMENT /1-GOP-13.1 ALTERNATE CORE COOLING (2.7/3.1)

METHOD ASSESSMENT GUIDELINES Calculate time to boiling.

N,CLR ASSESS PERSONNEL EXPOSURE Radiation Control GEN2.3.4 (2.5/3.1)

Determine path with lowest total dose.

Emergency Plan D,CLR,P EPIP-1.01 EMERGENCY MANAGER CONTROLLING GEN 2.4.29 PROCEDURE GEN 2.4.44 Determine highest EPIP classification.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the admin istrative topics, when all 5 are required.

  • Type Codes &Criteria:(C)ontrol room (CLR) Classroom (D)irect from bank.( 3 for ROs;. 4 for SROs & RO retakes)

(N)ew or (M)odified from bank.( 1)

(P)revious 2 exams.( 1; randomly selected) (Similar Topic)

(S)imulator

NAPS Admin-1 A Page 1 of 8 r...-t-.

rc'"~-~

,~

f'_.~

t

-." J REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-1A 1-PT-23, QUADRANT POWER TILT RATIO DETERMINATION REVIEW CANDIDATE EXAMINER

NAPS Admin-1A Page 2 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

1-PT-23, QUADRANT POWER TILT RATIO DETERMINATION REVIEW Alternate Path:

Yes. determine that a math error was performed Facility JPM #:

NIA KIA Rating(s):

Gen 2.1.23 (3.9/4.0) 015-A1.04 (3.5/3.7)

Task Standard:

1-PT-23 is reviewed and determined to have a math error on N-44 upper QPTA.

Preferred Evaluation Location:

Simulator __ Classroom X

References:

1-PT-23. QUADRENT POWER TILT RATIO DETERMINATION Validation Time:

15 min.

Preferred Evaluation Method:

Perform _X_ Simulate Time Critical: NO

=======================================================================

Candidate:

NAME Performance Rating:

SAT UNSAT __

Time Start:

Time Finish:

Performance Time __

Examiner:

NAME SIGNATURE 1

DATE

=======================================================================

COMMENTS

N/A SIMULATOR OPERATOR INSTRUCTIONS:

NAPS Admin-1A Page 3 of 8

NAPS Admin-1A Page 4 of 8 Tools/Equipment/Procedures Needed:

1-PT-23, QUADRENT POWER TILT RATIO DETERMINATION Calculator READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Reactor power is stable at 100%.

The unit supervisor desired a hand-calculated QPTR be performed on unit 1 The Unit 1 OATC has just completed 1-PT-23, QUADRENT POWER TILT RATIO DETERMINATION up through step 4 of Attachment 2, QPTR Hand Calculation.

INITIATING CUES:

You are to perform step 5 of Attachment 2, QPTR Hand Calculation.

TIME CRITICAL N/A

START TIME:

NAPS Admin-1 A Page 5 of 8 STEP 1:

Verify Current Reading for upper channels.

STANDARD:

Verifies entered data matches given data for all 4 upper channels.

SAT COMMENTS:

UNSAT STEP 2:

Verify Expected Current for upper channels.

STANDARD:

Verifies entered data matches given data for all 4 upper channels.

SAT COMMENTS:

UNSAT STEP 3:

Verify math for Normalized Current for upper channels.

STANDARD:

Verifies math performed properly for all 4 upper channels.

SAT COMMENTS:

UNSAT STEP 4:

Verify math for QPTR for upper channels.

CRITICAL STEP STANDARD:

Verifies math performed properly for all 4 upper channels and determines N-44 math error.

SAT COMMENTS:

UNSAT STEP 6:

Verify Current Reading for lower channels.

STANDARD:

Verifies entered data matches given data for all 4 lower channels.

SAT COMMENTS:

UNSAT

NAPS Admin-1A P

6 f 8 aae 0

STEP 7:

Verify Expected Current for lower channels.

STANDARD:

Verifies entered data matches given data for all 4 lower channels.

SAT COMMENTS:

UNSAT STEP 8:

Verify math for Normalized Current for lower channels.

STANDARD:

Verifies math performed properly for all 4 lower channels.

SAT COMMENTS:

UNSAT STEP 9:

Verify math for QPTR for lower channels.

STANDARD:

Verifies math performed properly for all 4 lower channels.

SAT COMMENTS:

UNSAT END OF TASK TIME STOP:

NAPS Admin-1A Page 7 of 8 CRITICAL STEP EXPLANATIONS:

STEP #

Explanation 4

Step is necessary, the operator must identify that math error occurred (inverted numbers).

NAPS Admin -1A Page 8 of 8 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Reactor power is stable at 100%.

The unit supervisor desired a hand-calculated QPTR be performed on unit 1 The Unit 1 OATC has just completed 1-PT-23, QUADRENT POWER TILT RATIO DETERMINATION, up through step 4 of Attachment 2, QPTR Hand Calculation.

INITIATING CUES:

You are to perform step 5 of Attachment 2, QPTR Hand Calculation.

TIME CRITICAL N/A

DOMINION North Anna Power Station (Page 2 of 3)

QPTR Hand Calculation 1-PT-23 Revision 28 Page 14 of 15 2.

IF one Power Range Channel is in trip OR the Unit 1 SRO desires that the current meters on the Power Range drawers be used, THEN read the current meters on the front of each operable Power Range upper and lower Detector Channel AND record the measured currents on Page 3 of this attachment.

3.

IF the Unit 1 PCS is operable AND the Unit 1 SRO desires to use the Unit 1 PCS to obtain Current Readings, THEN do the following:

3.1 Request a QPTR Report by doing the following on the Unit 1 PCS:

a.

Select the NSSS AND BOP button from the Main Screen.

b.

Select the QPTR button from the NSSS Menu Screen.

c.

Select the F4=Report button from the NI: Quadrant Power Tilt Ratio screen.

d.

IF using PCS, THEN select PRINT to print the QPTR Report.

3.2 WHEN the QPTR Report is complete, THEN remove the report from the printer.

3.3 Using the QPTR Report, record the appropriate current readings in the Current Reading spaces provided on Page 3 of this attachment.

4.

Complete the calculations on Page 3 of this attachment.

5.

Have a qualified individual complete an independent verification of all calculations.

, )

DOMINION North Anna Power Station (Page 3 of 3)

QPTR Hand Calculation 1-PT-23 Revision 28 Page 15 of 15 NOTE: Current Readings may be obtained from the face meters of the Power Range "B" Drawer OR from the test jacks OR from the Unit 1 PCS, if operable.

Avg. of Upper N-41 N-42 N-43 N-44 Normalized Description Upper Upper Upper Upper Currents Current Reading (record to nearest ua) i ~O,1ttc.;

Wt,q \\.\\

(",,7'~."i r!l left, I'.> \\

Expected Current (record as hown in Reactor Data Book or I~ I. "l,..

I-PT-22.4) lie:)

1 '1~,C\\

~ \\l.1..-

Normalized Current (Current Reading I Expected Current)

(4 decimal places)

, qC\\TL

,~"W

.q~,S

/1'10>

,Cf\\7..l QPTR (Normalized Current I Avg, of Norm. Currents)

./

Irjl;liil'~!II.l (4 decimal places)

I

')

,'\\C-\\(, \\

,qq~

I*(;o "L,-\\

Avg. of Lower N-41 N-42 N-43 N-44 Normalized Description Lower Lower Lower Lower Currents Current Reading (record to nearest J.1a)

IC\\ ~ 0 '

\\'1~. l. ~

?.l(.(.35' l..7.1. \\~'b Expected Current (record as shown in Reactor Data Book or I-PT-22.4)

M*

11".>

7\\1...1 l 1.),'-\\

ormalized Current (Current Reading I Expected Current)

\\~'"\\

(4 decimal places)

I,ozl.l I. ()

\\.u W $'" i. II 0

/, 0 '~ 4.

QPTR (Normalized Current I Avg. of Norm. Currents)

I,

\\.00 0 0 6 *;'<1(.

IfIJ~~~I'il~llltll (4 decimal places) c ; t:

D.~C{<t \\

Maximum QPTR:

Quadrant of Max QPTR:

(Record Maximum Upper or Lower QPTR Value from above)

(N41 Upper, N41 Lower N42 Upper, N42 Lower, etc.)

Completed by:

Date:

Verified by:

Date/Time Verification Completed:

(Use this Time for recording when surveillance is completed)

~.-/ k

.tf I REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-1B NAPS Admin-1B Page 1 of 8 CALCULATE THE MAXIMUM ALLOWABLE REACTOR VESSEL HYDROGEN VENTING TIME CANDIDATE EXAMINER

NAPS Admin-1 B Page 2 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

CALCULATE THE MAXIMUM ALLOWABLE REACTOR VESSEL HYDROGEN VENTING TIME Alternate Path:

No Facility JPM #:

KIA Rating(s):

G2.1.25 (2.8/3.1)

Standards Allowable vent time calculated lAW FR-1.3. Attachment 1 to be 1.52 minutes or 1 minute 31 seconds (1.47 -

1.57 acceptable).

Preferred Evaluation Location:

Preferred Evaluation Method:

Perform _X_ Simulate x

Simulator Classroom _~_

References:

FR-1.3. Response to Voids in Reactor Vessel, Attachments 1 and 2, Rev. 11.

Validation Time:

15 min.

Time Critical: NQ

=======================================================================

Candidate:

NAME Time Start:

Time Finish:

Performance Rating:

SAT UNSAT Performance Time DATE SIGNATURE NAME Examiner:

=======================================================================

COMMENTS

NAPS Admin-1B Page 3 of 8 Tools/Equipment/Procedures Needed:

FR-1.3, Response to Void in Reactor Vessel, attachments 1 and 2.

Calculator READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

Initial Conditions A SBLOCA has occurred on Unit 1.

1-FR-1.3, Response to Voids in Reactor Vessel, has been implemented and completed through subsequent step 21.

Containment Pressure - 9 psia Containment Temperature - 140°F H2 Concentration - 1.8%

RCS Pressure - 1500 psig Initiatinq Cues Calculate maximum allowable reactor vessel hydrogen venting time using FR-1.3, Attachments 1 and 2.

When you finish the actions necessary to accomplish this, please inform an examiner.

NAPS Admin-1B Page 4 of 8 Perfonnance Checklist Notes to the Evaluator.

Task critical elements are denoted by an asterisk (*). If substeps of a critical element also have an asterisk

(*), then only those asterisked substeps are critical to performance of that task element.

Critical step sequencing requirements: 1 & 2 (any order) before 3; 3 &4 (any order) before 5.

START TIME:

  • Step 1 DETERMINE CONTAINMENT VOLUME (STP).

CRITICAL STEP Standards a)

Determines containment temperature from Initial Conditions.

b)

Converts containment temperature in of to "H. (140°F + 460 = 6000R)

SAT c)

Determines containment pressure from Initial Conditions.

d)

Inserts containment pressure and oR into formula.

  • e)

Determines Containment volume (ref: 9.137 x 105 Cu Ft).

UNSAT Evaluator's Note

    • Thisstep is sequence critical. **

Evaluator's Comments

  • Step 2 DETERMINE MAXIMUM HYDROGEN VOLUME TO BE VENTED.

CRITICAL STEP Standards a)

Inserts H2 concentration and containment volume into formula.

  • b)

Determines max H2 volume to be vented. (Ref: 10964 Cu Ft).

SAT Evaluator's Note

    • This step is sequence critical...,.

UNSAT Evaluator's Comments

  • Step 3 DETERMINE HYDROGEN FLOW RATE BASED ON RCS PRESSURE Standard a)

Consults Attachment 2 to determine hydrogen flow rate.

b)

Determines RCS pressure from Initial Conditions.

c)

  • Based on RCS pressure of 1500 psig, determines flow rate (Ref: 7200 +/- 100 scfm).

Evaluator's Note

    • This step is sequence cmicei" Evaluator's Comments
  • Step 4 CALCULATE MAXIMUM VENT PERIOD.

Standard 1.

Recalls maximum H2 volume to be vented and inserts into formula.

2.

Recalls H2 tlowrate and inserts into formula.

  • c)

Calculates venting period as 1.52 minutes or 1 minute 31 seconds (1.47 - 1.57 acceptable).

Evaluator's Note

    • This step is sequence critical. **

Evaluator's Comments NAPS Admin-1 B Page 5 of 8 CRITICAL STEP

_SAT

_UNSAT CRITICAL STEP

_SAT

_UNSAT

Step 6 REPORTTO NUCLEAR SHIFT MANAGER(EVALUATOR).

Standard Verbalstatus report made of task completion.

STOP TIME:

Evaluator's Comments NAPS Admin-1B Page6 of 8

___ SAT

___ UNSAT

STEP #

1 2

3 4

CRITICAL STEP EXPLANATIONS:

Explanation Required to calculate containment volume.

Required to calculate volume of hydrogen to be vented.

Required to determine flow rate.

Required to calculate flow period.

NAPS Admin-1 B Page 7 of 8

NAPS Admin-1B Page 8 of 8 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

Initial Conditions A SBLOCA has occurred on Unit 1.

1-FR-1.3, Response to Voids in Reactor Vessel, has been implemented and completed through subsequent step 21.

Containment Pressure - 9 psia Containment Temperature - 140°F H2 Concentration - 1.8%

RCS Pressure - 1500 psig Initiating Cues Calculate maximum allowable reactor vessel hydrogen venting time using FR-1.3, Attachments 1 and 2.

When you finish the actions necessary to accomplish this, please inform an examiner.

Procedure: 1-FR-I.3 Rev: 011 PAR: 0

Title:

RESPONSE TO VOIDS IN REACTOR VESSEL Effective Date:

03/30/2004 Station:

North Anna CONTINUOUS USE

VIRGINIA POWER NORTH ANNA POWER STATION FUNCTION RESTORATION PROCEDURE NUMBER PROCEDURE TITLE REVISION 1-FR-1. 3 RESPONSE TO VOIDS IN REACTOR VESSEL 11 PAGE (WITH TWO ATTACHMENTS) 1 of 14 PURPOSE To provide instructions to respond t o voids in the Reactor Vessel Head.

ENTRY CONDITIONS This procedure is entered from:

Yellow terminus of the INVENTORY CSF STATUS TREE.

RECOMMENDED APPROVAL:

RECOMMENDED APPROVAL - ON FILE APPROVAL:

APPROVAL - ON FILE DATE DATE EFFECTIVE DATE

NUMBER PROCEDURE TITLE REVISION 11 1-FR-1. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 2 of 14 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION:

If a controlled natural circulation cooldown is in progress and a void in the Reactor Vessel Upper Head is expected. then this procedure should not be performed.

NOTE:

Setpoints in brackets [ ] are for adverse Containment atmosphere (20 psia Containment pressure or Containment Radiation has reached or exceeded 10 5 R/hr or 70% on High Range Recorder).

l~

CHECK IF SI IS TERMINATED

.~ SI FLOW ISOLATED 2~ CHECK AT LEAST ONE CHARGING PUMP -

  • u RUNNING RETURN TO procedure and step in effect.

Do the following:

a)

IF CC flow to any RCP Thermal Barrier is NOT indicated.

THEN locally isolate seal inj ection to the affected RCPs:

  • l-CH-3l8. A RCP Seal Injection Isolation Valve
  • 1 CH-3l4. B RCP Seal Injection Isolation Valve
  • l-CH-3l0. C RCP Seal Injection Isolation Valve b) Open l-CH-MOV 1373. Charging Pump Recirc Header Isolation Valve.

c) Establish recirc path for the Charging Pump to be started:

  • l-CH-MOV-1275A (l-CH-P-lA)
  • l-CH-MOV-1275B (l-CH-P-lB)
  • l-CH-MOV-1275C (l-CH-P-lC) d) Start one Charging Pump.

NUMBER PROCEDURE TITLE REVISION 11 1-FR-1. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 3 of 14 ACTION/EXPECTED RESPONSE ESTABLISH INSTRUMENT AIR TO CONTAINMENT:

RESPONSE NOT OBTAINED a) Verify at least one Air Compressor is supplying Instrument Air System b) Verify Containment Instrument Air Trip Valves - OPEN:

  • 1-IA-TV-102A
  • 1-IA-TV-102B 4~ CHECK CHARGING FLOW - AT LEAST

() 25 GPM INDICATED a) Start at least one Air Compressor.

b)

Do the Following:

1) Reset both trains of Phase B Isolation if necessary.
2) Manually open valves.

Establish charging:

a)

Put controller for 1-CH-FCV-1122 in MANUAL and close.

b) Close 1-CH-HCV-1311, Auxiliary Spray Valve.

c) Open Normal Charging Line Isolation Valves:

.1-CH-HCV-1310

  • 1-CH-MOV-1289A
  • l-CH-MOV-1289B d) Open 1-CH-FCV-1122 to establish 25 gpm charging flow IF 25 gpm Charging can NOT be established, THEN RETURN TO procedure and step in effect.

NUMBER PROCEDURE TITLE REVISION 11 1-FR-1. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 4 of 14 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

~ CHECK CC SYSTEM STATUS:

a) Check CDA - NOT ACTUATED b) Verify Service Water Supply Valves to CC System - OPEN:

  • I-SW-MOV-108A
  • I-SW-MOV-I08B c) Verify at least one CC Pump -

RUNNING a)

WHEN either of the following conditions are met, THEN continue with Steps 5b and 5c:

  • Service Water flow through Recirc Spray Heat Exchangers is secured
  • TSC or Plant Staff has determined that Service Water System capacity is sufficient to supply CC Heat Exchangers b) Manually open valves.

WHEN Service Water is restored to CC Heat Exchangers.

THEN continue with Step 5c.

c)

Perform the following:

1) IF a CDA has occurred.

THEN close the Stub Bus Tie BraakarI s ).

2) Start at least one CC Pump using I-OP-51.1.

COMPONENT COOLING SYSTEM.

IF at least one CC Pump cannot be started.

THEN restore CC System using l-AP-15, LOSS OF COMPONENT COOLING.

WHEN CC is established.

THEN perform Step 6.

Continue with Step 7.

NUMBER PROCEDURE TITLE REVISION 11 1-FR-1. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 5 of 14 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6~ CHECK LETDOWN IN SERVICE:

Establish letdown:

a)

Put l-CH-PCV-1145 in MANUAL and open to 100%.

b) Open the following:

  • l-CH-TV-1204A
  • 1-CH-TV-1204B
  • 1-CH-LCV-1460A
  • l-CH-LCV-1460B c) Open one of the following Letdown Orifice Valves:
  • l-CH-HCV-1200A
  • 1-CH-HCV-1200B
  • l-CH-HCV-1200C d) Adjust 1-CH-PCV-1145 to establish 300 psig letdown pressure and put in AUTO.

IF Letdown can NOT be established.

THEN establish excess letdown using 1-0P-8.5. OPERATION OF EXCESS LETDOWN.

GO TO Step 7.

NUMBER PROCEDURE TITLE REVIS I ON 11 1-FR-1. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 6 of 14 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7~ ESTABLISH STABLE RCS CONDITIONS:

a)

PRZR level

- GREATER THAN 69%

[72%]

b)

RCS pressure - STABLE c) Hot Leg t emperatures - STABLE 8~ CHECK RCP SEAL COOLING :

  • Thermal barrier - FLOW INDICATED
  • Seal i nj ection - FLOW INDICATED 9~

MAINTAIN SEAL INJECTION FLOWTO

~ EACH RCP BETWEEN 6 GPM AND 8 GPM 10~ CHECK RCPs - ALL STOPPED a)

Control charging and letdown as required to stabilize PRZR level.

b) Energi ze PRZR heaters and us e normal sp ray as requLred to stabilize RCS pressure.

IF normal spray i s NOT availabl e AND letdown is i n servi ce.

THEN use Auxil i ary Spray.

c) Dump steam as re qUired to stabi l ize Hot Leg t emperatures.

IF one fl ow is indicated.

THEN re-est ablish the other flow.

IF no flow is i ndi cat ed.

THEN i ni t i ate 1-AP-33. 2. LOSS OF RCP SEAL COOLING.

GO TO Step 16.

NUMBER PROCEDURE TITLE REVISION 11 1-FR-I. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 7 of 14 ACTION/EXPECTED RESPONSE CHECK IF RCS PRESSURE SHOULD BE INCREASED:

RESPONSE NOT OBTAINED a)

RCS pressure - AT LEAST 100 psi LESS THAN TECH SPEC LIMIT 3.4.3. Figure 3.4.3 -2 b)

RCS pressure - LESS THAN 1850 PSIG [2000 PSIG]

c) Energize PRZR Heaters to increase RCS pressure 50 psi AND stabilize RCS pressure 12~

CONTROL CHARGING AND LETDOWN FLOW

.~ TO MAINTAIN PRZR LEVEL GREATER THAN 36% [40%]

13~ CHECK RVLIS UPPER RANGE INDICATION,

a)

Indication - INCREASING b) Indication - GREATER THAN 95%

c) Turn off PRZR Heaters as required to stabilize RCS pressure d)

RETURN TO procedure and step in effect a)

GO TO Step 14.

b)

GO TO Step 14.

a)

GO TO Step 14.

b)

RETURN TO Step 11.

NUMBER PROCEDURE TITLE REVISION 11 1-FR-I. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 8 of 14 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION:

Following a loss of all seal cooling, affected RCPs should not be started without prior status evaluation.

NOTE:

  • Normal PRZR spray should be isolated from any RCP that is stopped.
  • RCPs should be run in the following order of priority to provide PRZR spray:

C. A.

14~ TRY TO START ONE Rep, a) Consult TSC or Plant Staff to determine if RCS non-condensible gas concent rat ion -

ACCEPTABLE FOR RCP START b) Establish the f ollowing conditions before starting an RCP :

  • PRZR level - GREATER THAN 69%

[72%]

  • RCS subcooling based on Core Exit TCs - GREATER THAN 50°F

[l00° F]

  • Use PRZR heaters as necessary to saturate the pressurizer water c) Start one RCP using 1-0P-S.2, REACTOR COOLANT PUMP STARTUP AND SHUTDOWN a)

GO TO Step 16.

b)

IF conditions cannot be established.

THEN GO TO Step 16.

c)

GO TO Step 16.

NUMBER PROCEDURE TITLE REVISION 11 1-FR-1. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 9 of 14 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15\\n? RVLIS INDICATION - LESS THAN VALUE

.'r-IN TABLE:

NO.

RVLIS INDICATION RCPs RUNNING UPPER RANGE DYNAMIC RANGE 0

95%

I 42%

16\\rlP VERIFY CONTAINMENT HYDROGEN

.n+- ANALYZER - IN SERVICE 17\\nf CHECK IF LOW PRZR PRESSURE SI CAN 0- BE BLOCKED:

a)

PRZR pressure LESS THAN 1950 PSIG b) Put both Low PRZR Pressure SI Block switches to BLOCK c) Check Annunciator Panel "P" G-4

- LIT 18~ RECORD RCS PRESSURE, 150 D psig GO TO Step 26.

Put Hydrogen Analyzer in service using 1-OP-63.2, CONTAINMENT HYDROGEN ANALYZER.

a) Reduce PRZR pressure to less than 1950 psig using normal PRZR spray.

IF normal spray is NOT available AND letdown is in

service, THEN use Auxiliary Spray.

IF Auxiliary Spray is NOT available.

THEN use one PRZR PORV.

NUMBER PROCEDURE TITLE REVISION 11 1-FR-1. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 10 of 14 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

,¥- ESTABLISH FOLLOWING RCS CONDITIONS:

a)

PRZR level - GREATER THAN 69%

[72%]

b)

RCS pressure - STABLE c)

RCS subcooling based on Core Exit TCs - GREATER THAN 75°F

[125° F]

d) Hot Leg temperatures - STABLE a)

Control charging and letdown as required.

b) Energize PRZR Heaters and use normal spray as required.

IF normal spray is NOT available AND letdown is i n service.

THEN use Auxiliary Spray.

c)

Dump steam as required.

d)

Dump steam as required.

NOTE:

  • This procedure should be continued while hydrogen sample is obtained in Step 20.
  • There is a delay time of 5 minutes before the Containment Hydrogen Analyzer will provide an accurate reading.

20~ CHECK CONTAINMENT HYDROGEN

\\f CONCENTRATION:

a) Verify Hydrogen Analyzer - IN SERVICE b) Hydrogen concentration - LESS THAN 4%

c) Hydrogen concentration - LESS THAN 0.5%

a) Put Hydrogen Analyzer in service usi ng 1-0P -63.2.

CONTAINMENT HYDROGEN ANALYZER.

b) Consult TSC or Plant Staff for additional recovery actions.

GO TO Step 21.

c)

IF hydrogen concentration i s less than 4%.

THEN put Hydrogen Recombiner in service using 1-0P -63.1.

POST ACCIDENT THERMAL HYDROGEN RECOMBINER.

NUMBER PROCEDURE TITLE REVISION 11 1-FR-1. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 11 of 14 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 21~~ PREPARE CONTAINMENT FOR REACTOR

.]t-VESSEL VENTING:

a) Check Containment Purge and Exhaust Valves - CLOSED b) Start Containment Air Recirculation Equipment:

  • Containment Air Recirc Fans
  • Containment DOOle Fans 22.

DETERMINE MAXIMUM ALLOWABLE VENTING TIME:

a) Containment hydrogen concentration - LESS THAN 4%

b) Containment pressure - LESS THAN 20 PSIA c) Refer to Attachment 1 to determine maximum venting time a) Manually close valves.

a) Consult TSC or Plant Staff.

GO TO Step 22b.

b) Consult TSC or Plant Staff.

GO TO Step 23.

NUMBER PROCEDURE TITLE REVIS ION 11 1-FR-1. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 12 of 14 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23.

REVIEW REACTOR VESSEL VENTING TERMINATION CRITERIA:

  • RCS subcooling based on Core Exit TCs - LESS THAN 25°F [75°F]

PRZR level - LESS THAN 36% [40%]

  • RCS pres sure - DECREASES BY 200 PS I
  • Venting t ime - GREATER THAN MAXIMUM TIME CALCULATED IN STEP 22
  • RVLIS i ndicat i on - GREATER THAN OR EQUAL TO VALUE IN TABLE:

NO.

RVLIS INDICATION RCPs RUNNING UPPER RANGE DYNAMIC RANGE 0

95%

I 42%

2 61%

3 100%

  • RVLIS indication - NO INCREASING TREND

NUMBER PROCEDURE TITLE REVISION 11 1-FR-I. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 13 of 14 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION:

- Venting shoul d be stopped if any venting te rminat ion criterion in Step 23 is met.

- Opening Reactor Vent Valves coul d cause pressure trans i ents in the vent pipi ng. resulting i n s puri ous Reactor Vent Valve actuation.

24.

VENT REACTOR VESSEL:

a) Open both Reactor Vent Valves in one vent path : RC-SOV-1 01A-2 and 1-RC-SOV -1 01A-1

- l -RC -SOV-1 01B-2 and 1-RC-SOV-1 01B-1 b) Any venting termination criterion - MET c) Close all React or Vent Val ve s: RC-SOV-1 01A-l

- l -RC-SOV-I OIA-2 RC-SOV-1 01B-1

- l -RC-SOV-1 01B-2 a)

IF either valve fails to open in one vent path.

THEN close both valves and open valves i n second path.

b) Continue venting.

WHEN any vent ing termination criteri on is met.

THEN do Step 24c.

NUMBER PROCEDURE TITLE REVISION 11 1-FR-1. 3 RESPONSE TO VOIDS IN REACTOR VESSEL PAGE 14 of 14 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25.

26.

CHECK RVLIS INDICATION - GREATER THAN OR EQUAL TO VALUE IN TABLE :

NO.

RVLIS INDICATION RCPs RUNNING UPPER RANGE DYNAMIC RANGE 0

95%

I 42%

2 61%

3 100%

CHECK PRZR LEVEL - STABLE Raise RCS pressure to value recorded i n Step 18.

RETURN TO St ep 16.

Control charging and l etdown as required.

27.

RETURN TO PROCEDURE AND STEP IN EFFECT

- END -

NUMBER ATTACHMENT TITLE REVISION 1-FR-1. 3 11 INSTRUCTIONS FOR DETERMINING VENTING TIME ATTACHMENT PAGE 1

1 of 1 1.

Determine containment vol ume at STP A

where:

A (1. 82x1 06 cubic f t ) x p

x 14.7 psi a P (psi.a)

= Containment pressure (psLa)

T (degrees R)

= Containment temperature (degrees F) + 460 2.

Determine maximum hydrogen volume that can be vented B

B (3%

- Containment Hydrogen Concentration) x A 100%

3.

Determine hydrogen flow rate as a function of RCS pressure C

a.

Check RCS pressure.

b.

Using Attachment 2, read hydrogen flow rat e.

4.

Calculate maximum venting time (minutes):

Maximum venting time

~

C

NUMBER ATTACHMENT TITLE REVISION I -FR-1. 3 11 REACTOR HEAD VENT HYDROGEN ATTACHMENT FLOWRATE FOR VARIOUS RCS PRESSURES PAGE 2

1 of 1

FLOWRATE (SCFM) 10000 -'-''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''I'T'"'T''''''''''''''''''''''''''''''''''''''''''

9000 ~~-++-+++++++++-+-H-f-+l~-++-++++-++-++H-H-1-#t-++-++++++-++t 8000 ~~-++-++-+++++++-+-H-f-+l-H-++-++++-++-+-+-~H-1-H-++-++++++++t 7000 ~~-++-++-+++++++-+-H-f-+l-+-t-++-++++-~++H-H-1-+-t-++-++++++-++t 6000 -f-i-+-+-++++-+-+-t-t-1~++++++-H-f--M-+++++-+-+-+-H-I-+-+++++++H-l-H-I 5000 -H-+-+++++++t-H-+-++++++-¥~f-H++++++-H-f-+-+-++++++++t-H-+-H 4000 ~~-++-++-+++++++--hH-f-+l-+-t-++-++++-++-++H-H-1-H-++-++++++++t 3000 ~H-I-++-++-+++t:lIIH-+-+-H-f-+l-H-++-++++-++-+-+-H-H-1-H-++-++++++++t 2000 -H-+-+++-t-blH-t-H-+-+++++++t-Hf-H-t-I-++++-t-Hf-+-+-H++++H-I-H-+-H 1000 -f-i-+-tll'H-+++-+-H-I-H+++++-+-H-I-H-++++++H-IH-I-+++++++-+-H-1-H-1 o

250 500 750 1000 1250 1500 1750 2000 2250 2500 RCS PRESSURE (PS IG)

NAPS Admin-2 Page 1 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-2 O-PT-ao AC SOURCES OPERABILITY VERIFICATION CANDIDATE EXAMINER

NAPS Admin-2 Page 2 of 8 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

0-PT-80 AC SOURCES OPERABILITY VERIFICATION Alternate Path:

Yes, determine surveillance is unsat.

Facility JPM #:

KIA Rating(s):

GEN 2.2.12 (3.0/3.4)

Task Standard:

Determine that 1H 4160v bus voltage is out of specifications low.

Preferred Evaluation Location:

Simulator X

In-Plant

References:

0-PT-80 "AC SOURCES OPERABILITY VERIFICATION" TS-???

Validation Time:

15 min.

Preferred Evaluation Method:

Perform _X_ Simulate Time Critical: NO

=======================================================================

Candidate:

NAME Performance Rating:

SAT UNSAT Time Start:

Time Finish:

Performance Time Examiner:

NAME SIGNATURE

/

DATE

=======================================================================

COMMENTS

NAPS Admin-2 Page 3 of 8 SIMULATOR OPERATOR INSTRUCTIONS:

1. Recall tc # 2
2. Override meter for 1H Emergency Bus voltage to 0.81, meter should read approx. 4000.

NAPS Admin-2 Page 4 of 8 Tools/Equipment/Procedures Needed:

0-PT-80 "AC SOURCES OPERABILITY VERIFICATION" READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is stable at 100% power.

0-PT-80 "AC SOURCES OPERABILITY VERIFICATION" is scheduled to be completed during your shift for its normal weekly surveillance.

  • , Unit 2 Emergency busses has already been completed.

INITIATING CUES:

You are to complete 0-PT-80 "AC SOURCES OPERABILITY VERIFICATION".

TIME CRITICAL N/A

START TIME:

NAPS Admin-2 Page 5 of 8 STEP 1:

Review "Initial Conditions".

STANDARD:

Reviews section 3.0.

SAT COMMENTS:

UNSAT STEP 2:

Review "Precautions and Limitations".

STANDARD:

Reviews section 4.0.

SAT COMMENTS:

UNSAT STEP 3:

Perform Attachment 1, Unit 1 Emergency Buses.

CRITICAL STEP STANDARD:

During performance of completing attachment determines that 1H Emergency Bus voltage is out of specifications low.

SAT COMMENTS:

UNSAT STEP 4:

Perform Attachment 2, Unit 2 Emergency Buses.

STANDARD:

Already performed per initial conditions.

SAT COMMENTS:

UNSAT STEP 5:

Perform Attachment 3, Switchyard.

STANDARD:

Completes attachment.

SAT COMMENTS:

UNSAT

NAPS Admin-2 P

6 f 8 aQe a

STEP 6:

Perform section 7.1, "Acceptance Criteria".

STANDARD:

Determines that step 7.1.1 cannot be signed off.

SAT COMMENTS:

UNSAT STEP 6:

Perform section 7.2, "Follow-On Tasks".

CRITICAL STEP STANDARD:

Determines that step 7.2.1 cannot be signed off. Completes step 7.2.2.

SAT NOTE:

Inform candidate that another operator will enter the applicable Tech Spec Action along with any associated paperwork.

COMMENTS:

UNSAT STEP 7:

Perform section 7.3, "Completion Notification".

STANDARD:

Informs SRO that the test is complete.

SAT COMMENTS:

UNSAT END OF TASK TIME STOP:

NAPS Admin-2 Page 7 of 8 CRITICAL STEP EXPLANATIONS:

STEP #

Explanation 3

Required to determine that 1H bus voltage is below acceptable value.

6 Required to determine that test is unsat and that the 1H emergency bus is inoperable.

NAPS Admin-2 Page 8 of 8 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Unit 1 is stable at 100% power.

0-PT-80 "AC SOURCES OPERABILITY VERIFICATION" is scheduled to be completed during your shift for its normal weekly surveillance.

  • , Unit 2 Emergency busses has already been completed.

INITIATING CUES:

You are to complete 0-PT-80 "AC SOURCES OPERABILITY VERIFICATION".

TIME CRITICAL N/A

Procedure: O-PT-80 Rev:

007 PAR: 0

Title:

AC SOURCES OPERABILITY VERIFICATION Effective Date:

03/31/2006 Station:

North Anna CONTINUOUS USE

'Dominion-PROCEDURE NO:

o-PT-80 NORTH ANNA POWER STATION REVIS ION NO:

7 PROCEDURE TYPE:

UNIT NO:

OPERATIONS PERIODIC TEST 1&2 PROCEDURE TITLE :

AC SOURCES OPERABILITY VERIFICATION TEST FREQUENCY:

UNIT CONDITIONS REQUIRING TEST:

Weekly surveillance in Modes 1 through 6, during All modes or if EDG or normal offsite supply to emergency bus movement of recently Irradiated fuel assemblies, OR is Inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after entering Action of Tech Spec 3.8.1, and every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter SPECIAL CONDITIONS: None SURV REO REVISION

SUMMARY

  • FrameMaker Template 030.
  • Incorporated DCP 05-143 by deleting GITH5 and G102 being closed as an option when H502 is open on page 2 of Attachment 3. Added DCP 05-143 to References.
  • Incorporated E-PAR {PI } which replaced graphic on Attachment 1 with a new graphic showing alternate path for IH Bus operability through backfeed from B RSST and Bus 4 as long as the 11Bus is being fed from "A" RSST and Bus 5. Deleted P&L 4.3 that WHEN IH Emergency Bus is on Alternate Feed, THEN the IB Bus must be on Normal Feed to prevent both 1H and 11Bus from being supplied from 34.5 KV Bus 4. This PT does not establish plant electrical configurations, it verifies lineups.
  • Changed "Shift Supervisor" to "SRO" in Step 4.1 to comply with Operations Management title changes.

REASON FOR TEST (CHECK APPROPRIATE BOX):

['jO Surveillance D Post-Maintenance Work Order Number (Post-Maintenance Only):

TEST ~ERFO_~~~~IGNATURE):

DATE STARTED:

DATE COMPLETED:

\\...<Tt-ti.J.

TEST RftSULT (CHECK APPROPRIATE BOX):

WORK REQUEST NUMBERS AND DATE:

D Satisfactory D Unsatisfactory D Partial THE FOLLOWING PROBLEM(S) WERE ENCOUNTERED AND CORRECTIVE ACTIONS TAKEN :

(Use back for additional remarks.)

COGNIZANT SUPERVISOR or DESIGNEE:

DATE :

ADDITIONAL REVIEWS:

DATE:

CONTINUOUS USE

DOMINION North Anna Power Station TABLE OF CONTENTS Section 1.0 PURPOSE

2.0 REFERENCES

3.0 INITIAL CONDITIONS 4.0 PRECAUTIONS AND LIMITATIONS 5.0 SPECIAL TOOLS AND EQUIPMENT 6.0 INSTRUCTIONS 7.0 FOLLOW-ON ATTACHMENTS 1

Unit 1 Emergency Buses 2

Unit 2 Emergency Buses 3

Switchyard O-PT-80 Revision 7 Page 2 of 11 Page 3

3 4

4 4

5 5

8 9

10

DOMINION North Anna Power Station 1.0 O-PT-80 Revision 7 Page 3 of 11 PURPOSE To provide instructions for verifying two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Distribution System as required by Surveillance Requirements 3.8.1.1 and 3.8.2.1.

2.0 REFERENCES

2.1 Source Documents None 2.2 Technical Specifications 2.2.1 Tech Spec 3.8.1 2.2.2 Tech Spec 3.8.2 2.2.3 SR 3.8.1.1 2.2.4 SR 3.8.2.1 2.3 Technical References 2.3.1 11715-FE-1BB, One Line Diagram Electrical Distribution System 2.3.2 DCP-88-05, GDC-17 Third Station Reserve Transformer 2.3.3 Memo from K. S. Berger to J. A. Stall, dated 5-5-1989, North Anna Power Station Operation of 230-36.5KV Transformer 2.3.4 ET CEE 02-0005, Rev. 2, Voltage Specification For The Emergency AC Buses, North Anna Power Station, Unit 1 and 2 2.3.5 DCP 03-001, Installation Of 500/230 KV Transformer 6 and 230 KV Bus Rearrangement Project 2.3.6 DCP 05-143, Relocation of Switchyard Breaker H502, and Replacement of Switchyard Breakers G1TH5 and G102 / NAPS / Unit 1

DOMINION North Anna Power Station 2.4 Init Verif Commitment Documents None O-PT-80 Revision 7 Page 4 of 11 3.0 INITIAL CONDITIONS Notify the SRO of this test.

4.0 PRECAUTIONS AND LIMITAnONS 4.1 Comply with the following guidelines when marking steps N/A:

  • IF the conditional requirements of a step do not require the action to be performed, THEN mark the step N/A.
  • IF this test is being performed as a Partial PT or Post-Maintenance Test, THEN mark inappropriate steps N/A.
  • IF any other step is marked N/A, THEN have the SRO approve the N/A and submit a Procedure Action Request (PAR).

4.2 The following Tech Specs apply:

Operating

Shutdown 5.0 SPECIAL TOOLS AND EQUIPMENT None

DOMINION North Anna Power Station 6.0 O-PT-80 Revision 7 Page 5 of 11 INSTRUCTIONS NOTE: Attachment 1, Unit 1 Emergency Buses, Attachment 2, Unit 2 Emergency Buses, and Attachment 3, Switchyard, may be performed in any order and in conjunction with other attachments since Section 6.0 only gathers information, therefore order is not important.

NOTE: Verifying that a breaker is racked to test will satisfy the requirement for an open breaker.

NOTE: Verifying that a breakers' disconnects are open will satisfy the requirement for an open breaker.

Complete the following attachments by marking the appropriate box as the required condition is verified. IF the condition cannot be verified, THEN do not mark the box. WHEN an entire branch can be marked, THEN that condition is SAT.

  • Attachment 1, Unit 1 Emergency Buses
  • Attachment 2, Unit 2 Emergency Buses
  • Attachment 3, Switchyard 7.0 FOLLOW-ON 7.1 Acceptance Criteria NOTE: Utilize Attachment 1, Unit 1 Emergency Buses, Attachment 2, Unit 2 Emergency Buses, and Attachment 3, Switchyard to determine the following conditions.

7.1.1 IF Unit 1 is in Mode 1 - 4, THEN the 1H Emergency Bus AND 1J Emergency Bus are operable.

DOMINION North Anna Power Station 7.1.2 O-PT-80 Revision 7 Page 6 of 11 IF Unit 1 is in Mode 5, 6, Defueled, or during movement of recently irradiated fuel assemblies, THEN at least 1H Emergency Bus OR lJ Emergency Bus is operable.

7.1.3 IF Unit 2 is in Mode 1 - 4, THEN the 2H Emergency Bus AND 2J Emergency Bus are operable.

7.1.4 IF Unit 2 is in Mode 5, 6, Defueled, or during movement of recently irradiated fuel assemblies, THEN at least 2H Emergency Bus OR 2J Emergency Bus is operable.

7.1.5 T342 conditions are SAT.

7.1.6 500 KV line conditions are SAT.

7.1.7 230 KV to 34.5 KV Bus 5 line conditions are SAT.

7.2 Follow-On Tasks 7.2.1 IF the requirements of Steps 7.1.1 through 7.1.7 are satisfied, THEN mark the cover sheet SAT.

7.2.2 IF the requirements of Step 7.1.1, 7.1.2, 7.1.3, 7.1.4, OR 7.1.5 are NOT satisfied, THEN do the following:

a.

Declare the affected Bus inoperable. IF Step 7.1.5 is NOT satisfied, THEN both Busses are inoperable.

b.

Enter the applicable Action of Tech Spec 3.8.1 or Tech Spec 3.8.2.

c.

Record the inoperable Bus on the cover sheet.

d.

Mark the procedure cover sheet UNSAT.

DOMINION North Anna Power Station O-PT-80 Revision 7 Page 7 of 11 7.2.3 IF the requirement of Steps 7.1.6 or 7.1.7 are NOT satisfied, THEN do the following:

a.

Notify the SRO to determine, with Engineering Department assistance, if the necessary off-site power supply criteria is met.

b.

IF the SRO determines off-site power supply criteria is met, THEN mark the cover sheet SAT.

c.

IF the SRO determines off-site power supply criteria is NOT met, THEN mark the cover sheet UNSAT.

7.2.4 IF this procedure is NOT being performed for a weekly surveillance, THEN note the reason for procedure performance on Cover Page.

7.3 Completion Notification Notify the SRO that this test is complete.

Completed by:

Date:

DOMINION North Anna Power Station 1H Unit (Page 1 of 1) 1 Emergency Buses 34202 cpan O-PT-80 Revision 7 Page 8 of 11 Vottag8 UNIT 1 EMERGENCY BUSES Graph!cS No. CS2B378

DOMINION North Anna Power Station (Page 1 of 1)

Unit 2 Emergency Buses O-PT-80 Revision 7 Page 9 of 11 2H BRSST On Bus 4 242 Closed 252 Open 25H11 Closed 2H 2H Voltaqe 15E3 Frequency 4200-Closed 59.5-60.5 4400V

~

V2 i.\\")W Frequency Vo"age 25H1 Mode NotClosed 2H 1-4 in Connect Operable 2J 15F1 Closed 25J11 Closed 2J 2J Vo~ge 15F4 Frequency 4200-Closed 59.5-60.5 4400V (q{)

vru'P Frequency Vo"age 25H1 C RSST Mode NotClosed On 332 1-4 In Connect Bus3 Closed UNIT 2 EMERGENCY BUSES 34202 Open GraphicsNo.CS2838C

DOMINION North Anna Power Station Unit 1 In Mode 1-4 T342 Unit 2 In Mode 1-4 Both Units In ModeS, 6, D 500 KV Lines G202 G2T575 Closed Closed (Page 1 of 2)

Swltchyard T342 o en T342 SAT 0-PT-80 Revision 7 Page 10 of 11 575 Ladysmith 573 Morrisville 57502 Closed XT573 Closed 1--........-----------.1 2{ 3 57302 Closed WT'S76 Closed 500KV Line Conditions SAT 576 Midlothian --,---1 57602 Closed SWITCHYARD Graphics No. CS2839

DOMINION North Anna Power Station (Page 2 of 2)

Swltchyard O-PT-80 Revision 7 Page 11 of 11 BUS5 BUS5 No RSST Aligned to BUS5 BUS 5 H302 supplying Closed any RSST H3T255 Closed L5T255 Closed H502 Closed 230KV To 34.5 KV BUS 5 Line Conditions SAT H3TL6 Closed H602 Closed SWITCHYARD Gnophlcs No: SVll95B

CANDIDATE EXAMINER REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-3 ASSESS PERSONNEL EXPOSURE NAPS Admin -3 Page 1 of 7

NAPS Admin-3 Page 2 of 7 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

Assess Personnel Exposure - Determine path with lowest total dose.

Alternate Path:

N/A Facility JPM #:

N/A KIA Rating(s):

Gen 2.3.4 (2.5/3.1)

Task Standard:

Determines that Route 2 results in the lowest dose.

Preferred Evaluation Location:

Preferred Evaluation Method:

Perform _X_ Simulate x

Simulator Classroom _~_

References:

Advanced Radiation Worker Training Manual Level 2 Validation Time: 10 min.

Time Critical: NO

=======================================================================

Candidate:

NAME Time Start:

Time Finish:

Performance Ratina:

SAT UNSAT Performance Time DATE SIGNATURE

'/_---

NAME Examiner:

=======================================================================

COMMENTS

NONE SIMULATOR OPERATOR INSTRUCTIONS:

NAPS Admin-3 Page 3 of 7

NAPS Admin-3 Page 4 of 7 Tools/Equipment/Procedures Needed:

Calculator READ TO OPERATOR DIRECTIONS TO STUDENT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The crew is attempting to place a system in service, but they are unable to remotely open a valve.

You have been tasked with entering containment and locally opening the valve.

Health Physics personnel are currently unavailable to provide assistance.

Two routes are available to the valve:

o Route 1 consists of two segments.

Segment 1 has you walk through a 200mRlhr general field for 2 minutes.

Segment 2 has you walk in a 300 mRlhr general field to the valve for 8 minutes o

Route 2 consists of two segments.

Segment 1 has you walk through a 50 mRlhr general field for 4 minutes.

Segment 2 has you walk in a 150 mRlhr general field to the valve for 12 minutes o

The two routes as detailed are to be considered separately and are listed as the round-trip time to and from the manual valve.

INITIATING CUE:

You are to determine which route allows the lowest exposure.

NAPS Admin-3 Page 5 of 7 Note: Candidate may perform these steps in a different order however the calculated stay time should be correct.

START TIME:

STEP 1:

Calculate exposure from using Route 1.

CRITICAL STEP STANDARD:

Determine dose received from using Route 1.

SAT Segment 1 200 mRlhr

  • 1hr/60 min
  • 2 min = 62/3 mr Segment 2 UNSAT 300 mRlhr
  • 1hr/60 min
  • 8 min = 40 mr Total Dose 62/3 + 40 = 46 2/3 mr COMMENTS:

STEP 2:

Calculate exposure from using Route 2.

CRITICAL STEP STANDARD:

Determine dose received from using Route 2.

SAT Segment 2 50 mRlhr

  • 1hr/60min
  • 4 = 3 1/3 mr Segment 2 UNSAT 150 mRlhr
  • 1hr/60min
  • 12 min = 30 mr Total Dose 331/3 = 33 1/3 mr COMMENTS:

STEP 3:

Determine the lowest exposure path CRITICAL STEP STANDARD:

Compared results of calculations and determined that Route 2 to be the SAT lowest exposure.

COMMENTS:

UNSAT END OF TASK TIME STOP:

_

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