ML101520250

Initial Exam 2010-301 Final Administrative JPMs

ML101520250
Person / Time
Site:	Oconee
Issue date:	05/04/2010
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-269/10-301, 50-270/10-301, 50-287/10-301
Download: ML101520250 (137)

Text

REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-114 Admin-114 fnl Page 1 of 9 MODE CHANGE VERIFICATION FOR MODE 1&2 ENTRY RO CANDIDATE EXAMINER Mode Change Verification Alternate Path: No Facility JPM #: Admin-114 KIA Rating(s):

System: Generic KIA: 2.1.25 Rating: 3.9/4.2 Task Standard:

REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-114 fnl Page 2 of 9 Perform Mode change verification and identify that ONLY the following do not meet their acceptance criteria:

• SR 3.3.1.1 for RPS Instrumentation RC Temperature TH (A Loop) is not met.

• SR 16.5.13.1 for the CBAST is not met.

• SR 3.3.1.1 Dummy Bistable is installed Preferred Evaluation Location:

Preferred Evaluation Method: Simulator

_X_ In-Plant __ Perform X Simulate

References:

PT/1/A/06001001 B, Enclosure 13.23 Validation Time: 20 minutes Time Critical:

NO ====================================================================================

Candidate:

Time Start: ----NAME Time Finish: __ _ Performance Rating: SAT ___ UNSAT __ _ Performance Time: ----Examiner:

____________

_ ----------

_____

NAME SIGNATURE DATE ====================================================================================

COMMENTS SIMULATOR OPERATOR INSTRUCTIONS:

1. Recall Snap 213 2. Import files for ADMIN-114

3. Update CBAST Boron 10620 ppmB 4. Place Dummy Bistable Prop in B RPS Channel (RCP/flux trip) 5. Go to RUN Admin-114 fnl Page 3 of 9 Tools/Equipment/Procedures Needed: Admin-114 fnl Page 4 of 9 PT/1/A/06001001 B (Instrument Surveillance Prior To Mode Change) Enclosure 13.23, Entering Modes 1 & 2 From Mode 3 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 startup in progress Unit 1 in MODE 3 PT/1/A/0600/001 B (Instrument Surveillance Prior To Mode Change) Enclosure 13.23, (Entering Modes 1 & 2 From Mode 3) is in progress.

All control rod, APSR and related surveillances have been completed.

INITIATING CUES: The CR SRO directs you to complete PT/1/A/06001001 B (Instrument Surveillance Prior To Mode Change) Enclosure 13.23, Entering Modes 1 & 2 From Mode 3. Perform all surveillance that are not already signed off and once that is completed inform the SRO of ALL surveillances you performed whose acceptance criteria was NOT met.

START TIME: __ _ STEP 1: RPS Instrumentation RC Temperature TH (A Loop) Verify computer readouts agree within 3°F (If OAC unavailable, 5°F in RPS Cab). STANDARD:

Determine computer points DO NOT agree within 3°F by calling points up on the OAC. CUE: If candidate goes to RPS cabinet, inform them that the RPS cabinet agrees with the OAC computer points COMMENTS:

STEP 2: RPS Instrumentation RC Temperature TH (8 Loop) Verify computer readouts agree within 3°F (If OAC unavailable, 5°F in RPS Cab). STANDARD:

Determine computer points DO agree within 3°F by calling pOints up on the OAC. CUE: If candidate goes to RPS cabinet, inform them that the RPS cabinet agrees with the OAC computer pOints COMMENTS:

STEP 3: RPS Instrumentation RC Flow Verify total flow agrees within 4800 klbm/hr AND Verify NO computer alarms for high flow present. STANDARD:

Determine computer points DO agree within 4800 klbm/hr by calling points up on the OAC. Determine NO computer alarms for high flow present by observing the OAC alarm screen. COMMENTS:

Admin-114 fnl Page 5 of 9 CRITICAL STEP SAT -UNSAT -SAT -UNSAT -SAT -UNSAT -

STEP 4: CBAST Verify equivalency of 1100 ft3 of 11,000 ppm boron per OP/O/Al11 08/001 (Curves And General Information).

STANDARD:

Obtain CBAST level and boron concentration from the OAC or from Boron Board and CBAST level gauge. (66 inches and 10620 ppmB) Determine CBAST is in the inoperable range of Enclosure 4.15 (CBAST Concentration Vs. Level Curve) COMMENTS:

STEP 5: RPS Instrumentation RP RCP/Flux Trip Verify no Dummy Bistable installed.

Verify no trips present. Verify status annunciators operable (lamp test). STANDARD:

• Determines that Dummy Bistable is installed on 'B' RPS channel (RCP/flux trip). Verify no trips present by observing Statalarms on 1 SA-i. *Determines that 1 SA-5/E-2 (RP Channel B Dummy Bistable Inserted) does not illuminate when performing an annunciators lamp test. CUE: If candidate addresses possibility of burned out bulbs in 1SA-S/E-2 then inform them that we have replaced the light bulbs in 1 SA-S/E-2 with bulbs known to be good. COMMENTS:

STEP 6: RCS Loops Verify required RCPs (3 or 4) in operation with RCS flow indicated.

STANDARD:

Determine 4 RCPs are in operation by observing red on lights lit and normal pump amps. Determine RCS flow is indicated on RC Flow gauge on 1UB1. COMMENTS:

Admin-114 fnl Page 6 of 9 CRITICAL STEP SAT -UNSAT -*CRITICAL STEP SAT -UNSAT -SAT -UNSAT -

STEP 7: Inform CR SRO of any surveillances that are NOT met. STANDARD:

Candidate should determine that the following surveillances are not met.

• SR 3.3.1.1 for RPS Instrumentation RC Temperature TH (A Loop) is not met.

• SR 16.5.13.1 for the CBAST is not met.

• SR 3.3.1.1 Dummy Bistable is installed Cue: Ask candidate about any surveillances that were not met if not addressed.

COMMENTS:

END TASK STOP TIME: ____ _ Admin-114 fnl Page 7 of 9 CRITICAL STEP SAT UNSAT CRITICAL STEP EXPLANATIONS:

STEP # Explanation 1 This step is required to determine the condition is not met. 4 This step is required to determine the condition is not met. 5 This step is required to determine the condition is not met. 7 This step is required to inform surveillances NOT met. Admin-114 fnl Page 8 of 9 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS:

Unit 1 startup in progress Unit 1 in MODE 3 PT/1/A/06001001 B (Instrument Surveillance Prior To Mode Change) Enclosure 13.23, (Entering Modes 1 & 2 From Mode 3) is in progress.

All control rod, APSR and related surveillances have been completed.

INITIATING CUES: The CR SRO directs you to complete PT/1/A/06001001 B (Instrument Surveillance Prior To Mode Change) Enclosure 13.23, Entering Modes 1 & 2 From Mode 3. Perform all surveillance that are not already signed off and once that is completed inform the SRO of ALL surveillances you performed whose acceptance criteria was NOT met.

Duke Energy Procedure No. Oconee Nuclear Station PT/I/A/0600/001 B Instrument Surveillance Prior To Mode Change Revision No. 032 Electronic Reference No. Continuous Use OPOO964Z PERFORMANCE I * * * * * * * * *

• UNCONTROLLED FOR PRINT * * * * * * * * * * (ISSUED) -PDF Format PT/l1 A/0600/001 B Page 2 of5 Instrument Surveillance Prior To Mode Change 1. Purpose 1.1 To verifY proper operation of various instruments and systems prior to Mode change. 2. References

3. 4. 5. 6. 2.1 Technical Specifications (TS) 2.2 DPC/Oconee Nuclear Station Core Operating Limits Report (COLR) 2.3 UFSAR Chapter 16 Selected Licensee Commitments (SLC) Time Required 3.1 30 minutes Prerequisite Tests None Test Equipment None Limits And Precautions 6.1 PT/O/ A/0600/o0 1 A (Loss Of Computer) should be referred to upon a loss of computer or loss of a computer point or function needed for a surveillance.

PT/l1 A/06001001 B Page 3 of5 6.2 When using Computer Points to perform a surveillance, the Computer Points MUST be used from a Computer Display Screen, which also indicates the Quality of the Computer Point.

• Computer Point Quality and Value MUST indicate as follows to be used for a surveillance:

• GOOD with a Value that represents actual plant conditions

• INHB with a Value that represents actual plant conditions

• LALM with a Value that represents actual plant conditions

• HALM with a Value that represents actual plant conditions

• LOLO with a Value that represents actual plant conditions

• HIHI with a Value that represents actual plant conditions

• ALM with a Value that represents actual plant conditions.

7. Required Unit Status 7.1 Required Unit Mode stated in each enclosure.

8. Prerequisite System Conditions None 9. Test Method 9.1 Component checks will be made according to information given in the applicable enclosures.

10. Data Required 10.1 Data requirements specified in applicable Enclosures.

11. Acceptance Criteria 11.1 Systems or components meet TS or SLC requirements applicable to surveillance step.

PT/ll AI06001001 B Page 4 of5 12. Procedure 12.1 Perfonn component checks prior to changing Modes within the required time frames using the appropriate enclosure.

12.2 Instrument operation may be checked either by reading appropriate recorder, gauge, etc., or by selecting computer point ID where applicable.

12.3 Dixson Indicators 12.3.1 12.3.2 12.3.3 Dixsons listed on Enclosure "Dixson Meter Infonnation" are on an enhanced surveillance interval.

IF any Dixson listed on Enclosure "Dixson Meter Infonnation" are found to be blinking with a reading of zero, no action is required unless a failure is suspected.

Dixsons NOT listed on Enclosure "Dixson Meter Infonnation" are on a surveillance interval.

These Dixsons have alternate methods of verifying input signal is valid. 13. Enclosures 13.1 Entering Mode 2 From Mode 1 13.2 Entering Mode 3 From Modes 1 & 2 13.3 Surveillances Prior To ReS::; 325°F 13.4 Entering Mode 4 From Mode 3 13.5 Entering Mode 5 From Mode 4 13.6 Entering Mode 6 From Mode 5 13.7 Surveillances Prior To Fuel Movement In RB 13.8 Entering No Mode From Mode 6 13.9 Entering Mode 6 From No Mode PT;l/ A/06001001 B Page 5 of5 13.10 Surveillances Prior To FTC Level < 21.34 ft Above Top OfRxV Flange 13.11 Surveillances Prior To RxV Head Installed 13.12 Entering Mode 5 From Mode 6 13.13 Surveillances Prior To Two DHR Loops NOT Operable 13.14 Surveillances Prior To Closing Any CRD Breakers With CRD System Capable Of Rod Withdrawal 13.15 Entering Mode 4 From Mode 5 13.16 Surveillances Prior To SGs Required For Heat Removal 13.17 Entering Mode 3 From Mode 4 13.l8 Surveillances Prior To RCS > 325°F 13.19 Surveillances Prior To RCS > 350°F 13.20 Surveillances Prior To RCS 2:: 800 psig 13.21 Surveillances Prior To RCS 2:: 900 psig 13.22 Surveillances Prior To Main Steam Pressure 2:: 700 psig 13.23 Entering Modes 1 & 2 From Mode 3 13.24 Surveillances Prior To > 20% RTP 13.25 Surveillances Prior To > 40% RTP 13.26 Dixson Meter Information Appendix

1. Initial Conditions 1.1 Unit is in Mode 3. Review Limits And Precautions.

Enclosure 13.23 Entering Mode 1 & 2 From Mode 3 PT 11; AI0600/o0 1 B Page 1 of3 SRs are only valid for:::; 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> once enclosure is started. When> 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> from start time, a new enclosure is required.

Date and Time Enclosure started T vd.a. '::> I 0 7 L) 0 2. Procedure

2.1 Perform

instrument checks as specified.

COMPONENT SR 3.3.1.1 RPS Instrumentation RC Temperature T H (A Loop) SR 3.3.1.1 RPS Instrumentation RC Temperature T H (B Loop) SR 3.3.1.1 RPS Instrumentation RC Plow SR 3.1.6.1 APSR Alignment Limits SR 3.2.1.1 Regulating Rod Position Limits SR 3.2.1.2 Regulating Rod Position Limits Enclosure 13.23 Entering Mode 1 & 2 From Mode 3 PT 11; A/0600100 1 B Page 2 of3 INITIALS COMPUTER REQUIRED CONDITIONS 01A1692 Verify computer readouts agree within 3°P (If OlA1693 OAC unavailable, 5°P in RPS Cab). IF any of CR RCS temperature selectors are changed, notify Rx Engineering to evaluate and update Enclosure "Loop T V s. Reactor Power" ofPTIlIA/06001001 (Periodic Instrument Surveillance) for new selected inputs. 01A1694 Verify computer readouts agree within 3°P (If 01A1695 OAC unavailable, 5°P in RPS Cab). IF any of CR RCS temperature selectors are changed, notify Rx Engineering to evaluate and update Enclosure "Loop T V s. Reactor Power" of PT I 1 I A/0600100 1 (Periodic Instrument Surveillance) for new selected inputs. 01A1549 Verify total flow agrees within 4800 klbmlhr 01A0877 AND 01A1420 Verify NO computer alarms for high flow OlA17l2 present. c.p0 GDREG Verify position of each APSR within 6.5% of group average. C?0 GDREG Verify regulating rod groups within sequence and overlap limits in COLR.

GDREG Verify regulating rod groups within position limits on curve in COLR. -----_ .. _----_ ... _---

COMPONENT SR 3.1.4.1 Control Rod Group Alignment Limits SR 3.1.5.1 Safety Rod Position Limits SR 16.5.13.1 CBAST SR 3.3.1.1 RPS Instrumentation RP RCP/Flux Trip SR 3.1.7.1 Position Indicator Channels PI Panel SR3.4.4.1 RCS Loops Enclosure 13.23 Entering Mode 1 & 2 From Mode 3 PT /1; A/0600/o0 1 B Page 3 of3 INITIALS COMPUTER REQUIRED CONDITIONS GDREG Verify all Control Rods in each Group agree GD SAFETY within +/- 3.5% of group average. C(/w IF a Control Rod is > +/- 3.5% of its Group average, refer to OP/1IA11105/019 (Control Rod Drive System). CPW GD SAFETY Verify each safety rod fully withdrawn.

PI Panel 01E0161 Verify equivalency of 1100 ft3 of 11,000 ppm boron per OP/o/AlI10S/001 (Curves And General Information).

Verify no Dummy Bistable installed.

Verify no trips present. Verify status annunciators operable (lamp test). cpJ Verify all Relative Rod Position indications agree within 5% of Absolute Rod Position indications.

IF NOT, notify Duty Rx Engineer for evaluation of core parameters and recommended actions. Verify required RCPs (3 or 4) in operation with RCS flow indicated.

Duke Energy Oconee Nuclear Station Instrument Surveillance Prior To Mode Change Continuous Use PERFORMANCE * * * * * * * * *

• UNCONTROLLED FOR PRINT * * * * * * * * * *

-PDF Format Procedure No. PT/I/A/0600/001 B Revision No. 032 Electronic Reference No. OP00964Z PT/ll AI06001001 B Page 2 of5 Instrument Surveillance Prior To Mode Change 1. Purpose 1.1 To verify proper operation of various instruments and systems prior to Mode change. 2. References

3. 4. 5. 6. 2.1 Technical Specifications (TS) 2.2 DPCIOconee Nuclear Station Core Operating Limits Report (COLR) 2.3 UFSAR Chapter 16 Selected Licensee Commitments (SLC) Time Required 3.1 30 minutes Prerequisite Tests None Test Equipment None Limits And Precautions 6.1 PT/OI AI0600100 1 A (Loss Of Computer) should be referred to upon a loss of computer or loss of a computer point or function needed for a surveillance.

PTf1/ Af0600fOOl B Page 3 of5 6.2 When using Computer Points to perform a surveillance, the Computer Points MUST be used from a Computer Display Screen, which also indicates the Quality of the Computer Point.

• Computer Point Quality and Value MUST indicate as follows to be used for a surveillance:

• GOOD with a Value that represents actual plant conditions

• INHB with a Value that represents actual plant conditions

• LALM with a Value that represents actual plant conditions

• HALM with a Value that represents actual plant conditions

• LOLO with a Value that represents actual plant conditions

• HIHI with a Value that represents actual plant conditions

• ALM with a Value that represents actual plant conditions.

7. Required Unit Status 7.1 Required Unit Mode stated in each enclosure.

8. Prerequisite System Conditions None 9. Test Method 9.1 Component checks will be made according to information given in the applicable enclosures.

10. Data Required 10.1 Data requirements specified in applicable Enclosures.

11. Acceptance Criteria 11.1 Systems or components meet TS or SLC requirements applicable to surveillance step.

12. Procedure PT;l/ Al0600/001 B Page 4 of5 12.1 Perform component checks prior to changing Modes within the required time frames using the appropriate enclosure.

12.2 Instrument operation may be checked either by reading appropriate recorder, gauge, etc., or by selecting computer point ID where applicable.

12.3 Dixson Indicators 12.3.1 12.3.2 12.3.3 13. Enclosures Dixsons listed on Enclosure "Dixson Meter Information" are on an enhanced surveillance interval.

IF any Dixson listed on Enclosure "Dixson Meter Information" are found to be blinking with a reading of zero, no action is required unless a failure is suspected.

Dixsons NOT listed on Enclosure "Dixson Meter Information" are on a surveillance interval.

These Dixsons have alternate methods of verifying input signal is valid. l3.1 Entering Mode 2 From Mode 1 l3.2 Entering Mode 3 From Modes 1 & 2 13.3 Surveillances Prior To ReS 325°F l3.4 Entering Mode 4 From Mode 3 l3.5 Entering Mode 5 From Mode 4 l3.6 Entering Mode 6 From Mode 5 l3.7 Surveillances Prior To Fuel Movement In RB l3.8 Entering No Mode From Mode 6 13.9 Entering Mode 6 From No Mode PTf1/ Al0600fOOI B Page 5 of5 13.10 Surveillances Prior To FTC Level < 21.34 ft Above Top OfRxV Flange 13.11 Surveillances Prior To RxV Head Installed 13.12 Entering Mode 5 From Mode 6 13.13 Surveillances Prior To Two DHR Loops NOT Operable 13.14 Surveillances Prior To Closing Any CRD Breakers With CRD System Capable Of Rod Withdrawal 13.15 Entering Mode 4 From Mode 5 13.16 Surveillances Prior To SGs Required For Heat Removal 13.17 Entering Mode 3 From Mode 4 13.18 Surveillances Prior To RCS > 325°F 13.19 Surveillances Prior To RCS > 350°F 13.20 Surveillances Prior To RCS 800 psig 13.21 Surveillances Prior To RCS 900 psig 13.22 Surveillances Prior To Main Steam Pressure 700 psig 13.23 Entering Modes 1 & 2 From Mode 3 13.24 Surveillances Prior To> 20% RTP 13.25 Surveillances Prior To > 40% RTP 13.26 Dixson Meter Information Appendix

1. Initial Conditions

>< 1.1 X 1.2 Unit is in Mode 3. Review Limits And Precautions.

Enclosure 13.23 Entering Mode 1 & 2 From Mode 3 PT /1; A/0600/00 1 B Page 1 of3 NOTE: SRs are only valid for:::; 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> once enclosure is started. When> 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> from start time, a new enclosure is required.

41.3 Date and Time Enclosure started Tad / D 7 0 D 2. Procedure

2.1 Perform

instrument checks as specified.

COMPONENT SR 3.3.1.1 RPS Instrumentation RC Temperature TH (A Loop) SR 3.3.1.1 RPS Instrumentation RC Temperature T H (B Loop) SR 3.3.1.1 RPS Instrumentation RC Flow SR 3.1.6.1 APSR Alignment Limits SR 3.2.1.1 Regulating Rod Position Limits SR 3.2.1.2 Regulating Rod Position Limits Enclosure 13.23 Entering Mode 1 & 2 From Mode 3 PT/I/A/06001001 B Page 2 of3 INITIALS COMPUTER REQUIRED CONDITIONS OlA1692 Verify computer readouts agree within 3 of (If OlA1693 OAC unavailable, 5°F in RPS Cab). IF any of CR RCS temperature selectors are changed, notify Rx Engineering to evaluate and update Enclosure "Loop .6. T V s. Reactor Power" ofPTIl/AI06001001 (Periodic Instrument Surveillance) for new selected inputs. 01A1694 Verify computer readouts agree within 3 of (If S 01A1695 OAC unavailable, 5°F in RPS Cab). of=F IF any of CR RCS temperature selectors are changed, notify Rx Engineering to evaluate and update Enclosure "Loop .6. T V s. Reactor Power" ofPTIlIAl06001001 (Periodic Instrument Surveillance) for new selected inputs. S 01A1549 Verify total flow agrees within 4800 klbrnlhr D ff-01A0877 AND 01A1420 Verify NO computer alarms for high flow 01A1712 present. ex GDREG Verify position of each APSR within 6.5% of group average. b< GDREG Verify regulating rod groups within sequence and overlap limits in COLR. GDREG Verify regulating rod groups within position limits on curve in COLR.

COMPONENT SR 3.1.4.l Control Rod Group Alignment Limits SR 3.1.5.1 Safety Rod Position Limits SR l6.5.13.l CBAST SR 3.3.1.1 RPS Instrumentation RP RCP/Flux Trip SR 3.1.7.1 Position Indicator Channels PI Panel SR 3.4.4.1 RCS Loops Enclosure 13.23 Entering Mode 1 & 2 From Mode 3 PTil/A/0600100l B Page 3 of3 INITIALS COMPUTER REQUIRED CONDITIONS GDREG Verify all Control Rods in each Group agree GD SAFETY within +/- 3.5% of group average. IF a Control Rod is > +/- 3.5% of its Group average, refer to OPIlIAI1l05/0l9 (Control Rod Drive System). >< GD SAFETY Verify each safety rod fully withdrawn.

PI Panel OlE016l Verify equivalency of 1100 f1"' of 11,000 ppm boron per OP/O/AI11081001 (Curves And General Information).

Verify no Dummy Bistable installed.

Verify no trips present. Verify status annunciators operable (lamp test). Verify all Relative Rod Position indications agree within 5% of Absolute Rod Position indications.

IF NOT, notify Duty Rx Engineer for evaluation of core parameters and recommended actions. S Verify required RCPs (3 or 4) in operation with off RCS flow indicated.

REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin 113 ROOAJL,/ Admin 113 fnl Page 1 of 8 CALCULATE AN ESTIMATED CRITICAL ROD POSITION CANDIDATE EXAMINER REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Calculate an Estimated Critical Rod Position Alternate Path: No Facility JPM #: CRO-037 KIA Rating(s):

System: GEN KIA: 2.1.19 Rating: 3.9/3.8 Task Standard:

Admin 113 fnl Page 2 of 8 Calculated inserted rod worth must agree within +/- 5% wd of attached example. Preferred Evaluation Location:

Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate

References:

PT/1 IA/11 03/15 (Reactivity Balance Procedure), Encl. 13.4 (Computerized ECP Calculation)

Validation Time: 17 minutes Time Critical:

NO ====================================================================================

Candidate:

Time Start: ___ _ NAME Time Finish: ----Performance Rating: SAT ___ UNSAT __ _ Performance Time: ----Examiner:

____________

_ ----------

______ 1 __ --NAME SIGNATURE DATE ====================================================================================

COMMENTS SIMULATOR OPERATOR INSTRUCTIONS:

None Admin 113 fnl Page 3 of 8 Tools/Equipment/Procedures Needed: PT/1/A/1103/15 (Reactivity Balance Procedure), Enc!. 13.4 (Computerized ECP Calculation)

READ TO OPERATOR DIRECTION TO TRAINEE: Admin 113 fnl Page 4 of 8 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 operated from 1/15 -4/3 at 100% power 4/3 1000 -Forced reactor shutdown is commenced at 10%/hr EFPD = 127 Unit is NOT returning from a "Forced Outage" PRESENT CONDITIONS:

4/10 1400 Unit #1 Startup in progress RCS Boron = 1325 RCS Temperature

= 532°F. Group 8 positioned at 35% withdrawn INITIATING CUES: The Control Room SRO directs you to calculate an original estimated critical rod position for 3 hours0.125 days <br />0.0179 weeks <br />0.00411 months <br /> from the present time per PT/1 IA/11 03/15, Reactivity Balance Procedure. Print out the calculation once it is completed.

START TIME: __ _ STEP 1: Step 2.1 This enclosure must be performed twice -the second is the separate verification.

Circle whether this is the original or the verification.

STANDARD:

Candidate should circle "original" and N/A the bullet step. Continue to Step 2.2 COMMENTS:

I CAUTION: IF the power history information from the last equilibrium Xe/Sm condition is NOT input into the code, significant error may result. STEP 2: Step 2.2 Obtain the power history back to the last time of Xenon equilibrium to perform the Xenon calculation from a source such as PI Server, OAC, RO Log, etc. Attach actual power history to this enclosure.

STANDARD:

The candidate will indicate that he will obtain a power history from one of the listed sources. Cue: Direct the candidate to obtain power history from the JPM initial conditions.

Candidate indicates that he will attach the power history to this enclosure.

Cue: Consider the Candidate Cue sheet your power history and that it is attached as directed Continue to Step 2.3 COMMENTS:

I Admin 113 fnl Page 5 of 8 SAT -UNSAT -SAT -UNSAT -

Admin 113 fnl PaQe 6 of 8 STEP 3: Step 2.3 Open RhoCalc. SAT -STANDARD:

Candidate locates the RhoCalc icon on the PC and opens the program. Note: For the purposes of this JPM the RhoCalc program will already be open on UNSAT the computer.

-Continue to Step 2.5 COMMENTS:

STEP 4: Step 2.4 *CRITICAL STEP INPUT appropriate data for the estimated critical rod position calculation, select "Calculate ECP", and print. SAT -STANDARD:

Candidate inserts the data given to him into the program.

• Name -Candidates name UNSAT -* *RCS Temperature

-532°F * *Current Boron Concentration

-1325 ppm * *EFPD -127 * *Group 8 position -35% withdrawn

• *Power History: 4/3 @1 000 -100% 4/3 @2000-0% 4/10 @ 1700 -0% *Unit 1 must be selected prior to running the calcualtion

• The "Calculate ECP" button is pressed to run the calculation.

Critical rod limits must agree within +/- 5% of attached example. NOTE: The Candidate must also select the desired unit. This may be done before or after entering the other data Cue: If candidate attempts to open the HELP file on the top menu, provide the candidate with the hard copy of the HELP file that is attached.

COMMENTS:

END TASK STOP TIME: ____ _

CRITICAL STEP EXPLANATIONS:

STEP # Explanation Admin 113 fnl Page 7 of 8 4 Step is necessary because the candidate needs to perform this step for the computer to calculate the ECP to determine the expected rod positions for criticality.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS:

Unit 1 operated from 1/15 -4/3 at 100% power 4/3 1000 -Forced reactor shutdown is commenced at 10%/hr EFPD = 127 Unit is NOT returning from a "Forced Outage" PRESENT CONDITIONS:

4/10 1400 Unit #1 Startup in progress RCS Boron = 1325 RCS Temperature

= 532°F. Group 8 positioned at 35% withdrawn INITIATING CUES: Admin 113 fnl Page 8 of 8 The Control Room SRO directs you to calculate an original estimated critical rod position for 3 hours0.125 days <br />0.0179 weeks <br />0.00411 months <br /> from the present time per PT/1 /A/11 03/15, Reactivity Balance Procedure.

Print out the calculation once it is complete.

Duke Energy Procedure No. Oconee Nuclear Station PT/I/A/ll03/015 REACTIVITY BALANCE PROCEDURE (Unit 1) Revision No. 067 Electronic Reference No. Continuous Use OX002WBQ PERFORMANCE I * * * * * * * * *

• UNCONTROLLED FOR PRINT * * * * * * * * * * (ISSUED) -PDF Format Reactivity Balance Procedure

1. Purpose PT/l!AIlI03/015 Page 2 of8 1.1 To calculate the Boron concentration necessary to provide greater than I %

shutdown margin. 1.2 To calculate the actual shutdown margin when the reactor is shutdown.

1.3 To evaluate the available shutdown margin during power operation (e.g., in the event of an inoperable rod.) 1.4 To provide the minimum RCS Boron concentration required to ensure greater than 1 %

shutdown margin to perform the Control Rod Drive (CRD) patch verification (for initial startup following refueling).

1.5 To estimate the critical rod configuration or the critical Boron concentration prior to startup. 1.6 To provide a method for preventing inadvertent criticality using sub critical multiplication measurement.

1.7 To provide nominal APSR position.

1.8 To provide the Minimum RCS Boron-Concentration to maintain SSF Operability

2. References

2.1 Technical

Specifications:

1.1, Definitions

-Shutdown Margin 3.1.1, Shutdown Margin 3.1.4, Control Rod Group Alignment Limits 3.1.5, Safety Rod Position Limits 3.2.1, Regulating Rod Position Limits 3.3.9, Source Range Neutron Flux 3.9.1, Boron Concentration

2.2 Selected

Licensee Commitments:

16.13.4, Reactivity Anomaly 2.3 Unit 1 -Physics Test Manual (PTM), ONEI-0400-55 2.4 Unit 1 -Core Operating Limits Report (COLR), ONEI-0400-50

2.5 Nuclear

Systems Directive 304, Reactivity Management 2.6 Work Process Manual, Section 2.5, Testing 3. Time Required Two people -1 hour for most enclosures

4. Prerequisite Tests None 5. Test Equipment Personal computer (for computerized calculations)

6. Limits and Precautions PTll/A/1103/015 Page 3 of8 6.1 The results of this procedure are used to make important operational decisions, therefore this procedure affects core reactivity. (R.M.) 6.2 Appropriate corrections have been made per this procedure, or actual plant conditions must be the same as the reference conditions stated on the appropriate enclosure(s). (R.M.) 6.3 Separate verification is required for each calculation performed.

For hand calculations, this requires that two people separately complete the appropriate enclosures for the desired calculation to verify the results are in agreement.

For computerized calculations, this requires that two people separately run the computer code(s) or verify the input. (R.M.) 6.4 IF the power history information from the last equilibrium Xe/Sm condition is NOT input into the code, significant error may result. (R.M.) 6.5 Per Technical Specification 3.1.5 all safety rods (groups 1-4) must be fully withdrawn prior to MODE 2 entry (Keff> 0.99, SDM < 1 % ilKlK). (R.M.) 7. Required Unit Status None 8. Prerequisite System Conditions None

9. Test Method 9.1 Shutdown Boron Concentration:

PT/IIAl1103/015 Page 4 of8 Calculated in Enclosure 13.1, Shutdown Boron Concentration/Shutdown Margin Calculation, or 13.2, Computerized Shutdown Margin Calculation.

The shutdown Boron concentration provides a greater than 1.0%.6.KIK shutdown margin with the worst case stuck rod assumed to be out. A reference shutdown Boron concentration is obtained based on the cycle bumup, rod positions and RCS temperature.

The reactivity worths of Xenon, Samarium, and the inoperable rod penalty (if applicable) are converted into their equivalent Boron concentrations. (Credit is taken only for the minimum Xenon worth occurring in a specified time interval, which should not exceed 13 hours0.542 days <br />0.0774 weeks <br />0.0178 months <br />. The Shutdown Boron concentration is valid only during that time interval.

Due to uncertanities in the Xenon models, 0.8 times the Xenon and Samarium worth are used unless the RCS is below 450°F, in which case 0.5 times the Xenon and Samarium worths are used. Xenon and Samarium worths may be assumed to be zero for conservatism.)

These Boron concentrations are then applied to the reference Boron concentration to provide the required Boron concentration for a greater than 1.0% .L\KlK shutdown margin (i.e., the shutdown Boron concentration).

9.2 Shutdown

Margin Calculation while Shutdown:

Calculated in Enclosure 13.1, Shutdown Boron Concentration/Shutdown Margin Calculation or 13.2, Computerized Shutdown Margin Calculation.

The shutdown margin is the amount of reactivity by which the reactor is shutdown.

The worst case stuck rod is assumed to be out. If operating with a known inoperable rod, an additional penalty is applied to account for that rod. This penalty need not be applied when the reactor is shutdown if that rod can be confirmed to be fully inserted by redundant indications.

The shutdown Boron concentration must first be found per step 9.1. The actual Boron concentration is then subtracted from this concentration and the result converted to % .L\KlK. 1.0% .L\KlK is then subtracted from this value to obtain the shutdown margin, expressed in -% .L\KlK. A separate check for SSF RC Makeup System operability is performed, which takes credit for Xenon and requires the stuck rod penalty. This limit is shown in Enclosure 13.20, Minimum RCS Boron Concentration to Maintain SSF Operability.

PT/I/A/1103/015 Page 5 of8 Following a shutdown, Control Rod Position at the time of Shutdown may be used with the Rod Position Limit curves (in COLR) to verify at least 1 %

shutdown margin for the first 3 hours0.125 days <br />0.0179 weeks <br />0.00411 months <br /> following shutdown (provided RCS Temperature stays 2: 532°F and boron does not decrease).

This may be necessary for shutdowns with an inoperable rod, since the more conservative calculation method (in Enclosure 13.1, Shutdown Boron Concentration/Shutdown Margin Calculation, and 13.2, Computerized Shutdown Margin Calculation) may not show 1 %

shutdown margin immediately after shutdown.

Boration should begin immediately to be able to show 1 %

shutdown margin using the calculation method. 9.3 Shutdown Margin at Power: Verified in Enclosure 13.18, Shutdown Margin Calculation at Power. While at power, the available shutdown margin may be verified to be 2: 1 %

by using the Rod Position Limits curves (in COLR). Operation in the "Acceptable Region" of these curves ensures that the shutdown margin following a reactor trip will be 2: 1 %

with the worst stuck rod out. There are curves for 3 and 4 RCP operation, and curves for 0 and 1 inoperable rod. A dropped rod is considered inoperable for the purposes of providing shutdown margin while at power. 9.4 Estimated Critical Rod Position:

Calculated in Enclosure 13.4, Computerized Estimated Critical Rod Position Calculation.

The core excess reactivity is obtained based on the cycle bumup. The reactivity worths associated with Boron, Xenon, temperature correction (ifRCS temperature not at 532°F) and Samarium are then obtained and summed with the core excess reactivity.

The groups 5-7 positions are then determined for which the inserted rod worth when summed with all the above, yields a total core reactivity of 0.0%

The upper and lower rod position limits are then determined and the actual critical rod positions are recorded.

9.5 Estimated

Critical Boron Concentration:

Calculated in Enclosure 13.5, Computerized Estimated Critical Boron Calculation.

The core excess reactivity is obtained based on the cycle bumup. The reactivity worth associated with Xenon, temperature correction (ifRCS temperature not at 532°F), Samarium and the desired critical rod positions are summed with the core excess reactivity.

The Boron concentration is then determined for which its reactivity worth, when summed with all the above, yields a total core reactivity of 0.0%

9.6 Sub critical Multiplication Measurement:

PT/l!Al1103/015 Page 6 of8 Performed in 13.6, Computerized Subcritical Multiplication (11M) Measurement.

With Group 1 at 50% wd, an initial source range (SR) count rate (Co) is recorded.

During control rod withdrawals, new counts (C) are recorded and used to calculate 11M, or CJc. As criticality is approached, CIC o will approach infinity, and 11M will approach zero. Plotting 11M versus rod worth provides a rough indication of what rod position will yield a critical condition, and acts as an indication of premature criticality, or criticality more than 0.75%

below the Estimated Critical Position calculated in step 9A. 10. Data Required 10.1 For Xenon Worth: Core EFPD and power history to time of last equilibrium xenon. 10.2 For Shutdown Boron Concentration/Shutdown Margin Calculation:

Power History, Boron Concentration, RCS temperature, Core EFPD, Group 8 position, any inoperable rod penalty. 10.3 For Estimated Critical Rod Configuration:

Boron Concentration, RCS temperature, Core EFPD, Group 8 Position, and power history. lOA For Estimated Critical Boron Configuration:

RCS temperature, Core EFPD, desired critical rod configuration and power history. 10.5 For Subcritical Multiplication Measurement:

ECP Control Rod position, time safety groups must be fully withdrawn, Unit, Cycle, Beginning of Cycle (Yes/No), EFPD, Graph Notify Lines (Yes/No), Xenon Free (Yes/No), and source range (SR) count rate. 11. Acceptance Criteria 11.1 Separate verifications for Shutdown Boron shall agree within 10 ppmB. The more conservative Shutdown Boron Concentration calculation shall be used to ensure at least a 1.0% SK/K shutdown margin. 11.2 Separate verifications for Estimated Critical Boron shall agree within 10 ppm. 11.3 Separate verifications for Estimated Critical Positions shall agree within 5% wd. llA Acceptance criteria for 11M approach to critical:

Criticality is achieved within 0.75%

of the predicted critical rod position concentration.

11.5 Review criteria for 11M approach to critical:

Criticality achieved within of the predicted critical rod position for startups considered Xenon free, 0.5% review criteria for non-Xenon free startups.

12. Procedure Complete, or refer to, the appropriate enclosure(s):

Shutdown Margin Calculation while shutdown:

PT!l/Al1103/015 Page 7 of8 Enclosure 13.1, "Shutdown Boron Concentration/Shutdown Margin Calculation," or Enclosure 13.2 "Computerized Shutdown Margin Calculation" Estimated Critical Rod Position:

Enclosure 13.4, "Computerized Estimated Critical Rod Position Calculation" Estimated Critical Boron Concentration:

Enclosure 13.5, "Computerized Estimated Critical Boron Calculation" Computerized Sub critical Multiplication (11M) Measurement:

Enclosure 13.6, "Computerized Subcritical Multiplication (11M) Measurement" Refueling Outage Boron Concentrations:

Enclosure 13.13, "Refueling Outage Boron Concentrations" Required Control Rod Group 8 Position:

Enclosure 13.14, "Required Group 8 Position and Designed Cycle Length" Designed Cycle Length Information:

Enclosure 13.14, "Required Group 8 Position and Designed Cycle Length" Required Shutdown Margin: Enclosure 13.16, "Shutdown Margin Requirements" Shutdown Margin Calculation at power: Enclosure 13.18, "Shutdown Margin Calculation at Power" RCS Boron Concentration for SSF Operability:

Enclosure 13.20, "Minimum RCS Boron Concentration to Maintain SSF Operability" PT/I/AI1103/015 Page 8 of8 NOTE: Only the appropriate completed enclosures need be attached to the procedure cover sheet to be submitted for procedure completion.

13. Enclosures 13.1 Shutdown Boron Concentration/Shutdown Margin Calculation 13.2 Computerized Shutdown Margin Calculation 13.3 Computerized Shutdown Margin Calculation Documentation 13.4 Computerized Estimated Critical Rod Position Calculation 13.5 Computerized Estimated Critical Boron Calculation 13.6 Computerized Subcritical Multiplication (11M) Measurement 13.7 Core Excess Reactivity vs. Bumup 13.8 Differential Boron Worth vs. Bumup 13.9 Temperature Coefficient vs. RCS Boron Concentration 13.10 Shutdown Boron Concentration vs. Bumup (Group 1 @ 0% wd) 13.11 Shutdown Boron Concentration vs. Bumup (Group 1 @ 50% wd) 13.12 Inoperable Rod Penalty for Individual Inoperable Rod 13.13 Refueling Outage Boron Concentrations 13.14 Required Group 8 Position and Designed Cycle Length 13.15 Power Defect vs. Reactor Power 13.16 Shutdown Margin Requirements 13.17 Control Rod Group Worths for Control Rod Drop Time Testing 13.18 Shutdown Margin Calculation at Power 13.19 Group 7 Control Rod Worth 13.20 Minimum RCS Boron Concentration to Maintain SSF Operability Enclosure 13.4 PT/liAl1l03/0l5 Computerized Estimated Critical Rod Position Page 1 of 4 Calculation

1. Purpose The purpose of this enclosure is to calculate an estimated critical rod position to be used during unit start up. 2. Procedure Calculation Performed by: __ N_O'_fV\_e.

___ _

NOTE: This enclosure must be performed twice -the second is the separate verification.

Circle whether this is the original or the verification: Must be performed by a Licensed Operator (N/ A next bullet step) Separate Verification

-Must be performed by a Qualified Reactor Engineer (N/A steps 2.8-2.13 for Separate Verification)

The only acceptance criterion is that measured RCS % design flow is greater than that required.

RPS flows can be expected to deviate from baseline.

IF returning from a forced outage perform an RCS flow check using POWCALC.XLS AND attach results to this enclosure.

CAUTION: IF the power history information from the last equilibrium Xe/Sm condition is NOT input into the code, significant error may result. NOTE: IF conducting an initial cycle startup the power history is 0% F. P. IA 2.2 IF returning from a forced shutdown:

2.2.1 Obtain

the power history back to the last time of Xenon Equilibrium to perform the Xenon calculation from a source such as PI server, OAC Log, RO Log, etc. 2.2.2 Attach actual power history (from OAC log, TMS, PI Server, etc.) to this enclosure.

Open RhoCalc.

Enclosure 13.4 PTil/AI1103/015 Computerized Estimated Critical Rod Position Page 2 of 4 Calculation NOTE: 1. EFPD input into the code shall correspond to the "beginning of the power history", s;;Sa cJ 2.4 G", J 0+ -tctS Jc. 2.5 NOT the EFPD at the "effective time of calculation".

2. When choosing the input Boron concentration during transient Xenon conditions sufficient time must be factored in to allow for changes to be made to the RCS and PZR Boron concentration, samples to be taken, the time required to pull Groups I -4 to 100% wd, and any other time constraints noted by the OCC. 3. The ECP time shall run sufficiently into the future to determine if MODE 2 entry could occur with Group 5 < 0%. This time of occurrence is required in step 2.7 4. Estimated conditions (i.e. RCS Boron/Temperature) at the time of criticality may be used. Input appropriate data for the estimated critical rod position calculation, select "Calculate ECP", and print. Circle the appropriate response:

Were estimated conditions used for the ECP? YeslNo 2.6 Verify Separate Verifications agree on the ECP within 5%wd for all future time steps that have an ECP prediction.

Enclosure 13.4 PT!l/A11103/015 Computerized Estimated Critical Rod Position Page 3 of 4 Calculation CAUTION: 1. All safety Rods (Groups 1-4) must be fully withdrawn prior to the time that "Rod Posn @ Mode 2 Entry" (T.S. 3.1.5) column reaches Group 5 < 0%. T. S. 3.1.5 prohibits entering Mode 2 (Keff> 0.99, SDM <1 % dKlK) on the Safeties.

IF Groups 1 -4 can NOT be fully withdrawn prior to the "Rod Posn @ Mode 2 Entry" (T.S. 3.1.5) column indicating 5 < 0%, any in-progress approach to critical must be aborted AND the RCS borated sufficiently to meet T.S. 3.1.5 requirements.

2. IF the RCS is sufficiently borated to account for Xe decay to Xe free conditions, Step 2.7.2 may be N/A'ed because the T.S. 3.1.5 limit will NOT be reached AND Mode 2 (Keff> 0.99, SDM <1 % dKlK) will NOT be entered on the Safeties.

2.7 Complete

one of the following steps: 2.7.1 Verify that the RCS is sufficiently borated to account for Xe decay such that entry into T.S. 3.1.5 will NOT occur. 2.7.2 Document the time/date of the time step immediately prior to the first occurrence of"5 < 0%" in the "Rod Posn @ Mode 2 Entry" (T.S. 3.1.5) column of the ECP printout.

Time at which the safety rods must be fully withdrawn:

___ hours on ___ (date). 2.8 Discuss the results ofECP with the Control Room SRO. (N/A this step on separate verification calculation).

Control Room SRO ---------------

2.9 Attach

results ofECP to the procedure and tum the package over to the Control Room SRO. (N/A this step on separate verification calculation).

2.10 Fill in the actual critical rod configuration and notification limit check on the computer printout. (NI A this step on separate verification calculation).

NOTE: The notification lines of lIM.xls spreadsheet are the review and acceptance criteria of 11.4 and 11.5. IF these criteria are NOT met see the WPM section 2.5, Testing, Approach to Critical Rod Position.

2.11 Verify actual critical conditions are within 1/M.xls notification lines. (NI A this step on separate verification calculation.)

Enclosure 13.4 PT!l/A/1103/015 Computerized Estimated Critical Rod Position Page 4 of 4 Calculation NOTE: The Reactor Engineering mail code is ON03CY. 2.12 Forward the completed ECP, including all applicable enclosures and attachments, to Reactor Engineering. (N/A this step on the separate verification calculation.)

NOTE: The GO Nuclear Design Group requires the "Procedure Completion Approved" blank to be signed off prior to transmittal.

2.13 Transmit copy of completed ECP to GO Nuclear Design. (N/A this step on separate verification calculation.)

REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin 117 6620 Admin 117 fnl Page 1 of 9 Evaluate SSF-ASW operability based on Pressurizer Relief Valve leakage CANDIDATE EXAMINER REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin 117 fnl Page 2 of 9 Evaluate SSF-ASW operability based on Pressurizer Relief Valve leakage Alternate Path: No Facility JPM #: NEW KIA Rating(s):

System: GEN KIA: 2.1.7 Rating: 4.4/4.7 Task Standard:

Perform PT/2/A/061 01001 (Reactor Coolant Leakage) Attach. 13.5 (pzr Relief Valve Leakage Calculation) and determine that the SSF Aux Service Water System is inoperable.

Preferred Evaluation Location:

Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate

References:

PT/2/A/0610/001 (Reactor Coolant Leakage) Attach. 13.5 (pzr Relief Valve Leakage Calculation)

Validation Time: 15 minutes Time Critical:

NO ====================================================================================

Candidate:

Time Start: ___ _ NAME Time Finish: ---Performance Rating: SAT ___ UNSAT __ _ Performance Time: ----Examiner:

____________

_ NAME SIGNATURE DATE ====================================================================================

COMMENTS SIMULATOR OPERATOR INSTRUCTIONS:

None Admin 117 fnl Page 3 of 9 Tools/Equipment/Procedures Needed: PT/2/A/06101001 (Reactor Coolant Leakage) Attachment 13.5 (pzr Relief Valve Leakage Calculation)

READ TO OPERATOR DIRECTION TO TRAINEE: Admin 117 fnl Page 4 of 9 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:

PT/2/A/06101001 (Reactor Coolant Leakage) is in progress Pzr Relief Valve leakage exists Autolog is NOT available Unit 2 Pzr Steam Space Leakage Excel Calculation NOT available PT/2/A/06101001 (Reactor Coolant Leakage) Attachment 13.5 (pzr Relief Valve Leakage Calculation) has been completed up to step 5.6. INITIATING CUES: The Operation Shift Manger directs you to complete Attachment 13.5 (pzr Relief Valve Leakage Calculation) and determine SSF ASW Pump operability.

Begin at Step 5.6. Refer to attached data sheet STARTTIME:

__ _ STEP 1: Step 5.6 and 5.7 Perform the following to obtain the Pzr Relief valve Leak Rate ... STANDARD:

Candidate will perform calculation and determine that Pzr Steam Space Leakage=O.18gpm (0.16-0.20)

Note: Refer to attached key. Continue to Step 5.8 COMMENTS:

STEP 2: Step 5.8 Determine SSF ASW Pump operability:

• Refer to Autolog or contact I&E to determine operable SSF Pzr Heaters.

• Refer to TS Bases 3.10.1 to determine required Pzr heaters/Pzr leakage. STANDARD:

Determine that Autolog is NOT available and refer to the data sheet to determine that 16 heaters are operable.

Refer to TS Bases 3.10.1 (SSF) page 7. Determine that for Unit 2 and 16 heaters the maximum allowed Pzr Steam Space Leakage is 0.10 gpm. The calculated Pzr Steam Space Leakage is 0.18 gpm and hence the SSF ASW Pump is NOT operable.

Continue to Step 5.9 COMMENTS:

Admin 117 fnl Page 5 of 9 CRITICAL STEP SAT -UNSAT -CRITICAL STEP SAT -UNSAT -

Admin 117 fnl P f age 6 0 9 STEP 3: Step 5.9 *CRITICAL STEP IF SSF ASW System is inoperable due to excessive steam space leakage, perform the following:

SAT -* Enter TS 3.10.1 Condition

'A' for SSF ASW System inoperability .

• IF required, notify SPOC to restore Pzr Heaters per IP/O/S/02001037 (Pressurizer Heater Test and Surveillance).

-UNSAT STANDARD:

• Determine that TS 3.10.1 Condition

'A' for SSF ASW System inoperability must be entered and SSF ASW must be returned to service within 7 days. SPOC notify SPOC to restore Pzr Heaters per IP/O/S/02001037 (Pressurizer Heater Test and Surveillance).

System Duty Engineer is notified.

Continue to Step 5.10 COMMENTS:

STEP 4: Step 5.10 STANDARD:

Record Unit 2 Pzr Steam Space Leakage in Autolog. SAT -Cue: State that when Autolog is returned to service that the Unit 2 Pzr Steam Space Leakage would be recorded in Autolog. UNSAT -COMMENTS:

END TASK STOP TIME: ____ _

DATA SHEET QT Trend Initial QT level = 80.0 inches Final QT Level = 80.7 inches Time = 60 minutes SSF Pzr Heater Per I&E, number of Bank 2, Group B & C Pressurizer Heaters available

= 16 Admin 117 fnl Page 7 of 9 CRITICAL STEP EXPLANATIONS:

STEP # Explanation 1 Calculation required to determine SSF ASW Pump operability Admin 117 fnl Page 8 of 9 2 Step is necessary because the candidate needs to perform this step to determine that the SSF Aux Service Water pump is NOT operable.

3 Determining when SSF ASWP must be restored to OPERABLE CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS:

PT 121 A/061 01001 (Reactor Coolant Leakage) is in progress Pzr Relief Valve leakage exists Autolog is NOT available Unit 2 Pzr Steam Space Leakage Excel Calculation NOT available PT/2/A/06101001 (Reactor Coolant Leakage) Attachment 13.5 (pzr Relief Valve Leakage Calculation) has been completed up to step 5.6. INITIATING CUES: Admin 117 fnl Page 9 of 9 The Operation Shift Manger directs you to complete Attachment 13.5 (pzr Relief Valve Leakage Calculation) and determine SSF ASW Pump operability.

Begin at Step 5.6. Refer to attached data sheet Enclosure 13.5 Pzr Relief Valve Leakage Calculation

1. Initial Conditions Verify RCS Temperature AND Pressure stable. {17} 2. Procedure

{3} PT 121 A/060010 1 0 Page 1 of9 2.1 IF any RCP Seal Leakage Flow indicator is out of service, perform the following:

Notify Systems Engineering.

Person Notified Date 2.1.2 NI A remainder of this enclosure.

t.Q:J 2.2 Ensure weekly pressurizer boron sample has been requested.

{14} NOTE: Pzr Steam Space Leakage Excel Calculation available on OPS Web Page. JV I IF Unit 2 Pzr Steam Space Leakage Excel Calculation available, perform Section 3 (Unit 2 Pzr Steam Space Leakage Excel Calculation available).

2.4 IF Unit 2 Pzr Steam Space Leakage Excel Calculation NOT available, perform the following:

2.4.2 Refer

to Section 4 (Example OfRCP Seal Leakage Flow Trend History).

Perform Section 5 (Unit 2 Pzr Steam Space Leakage Excel Calculation NOT Available).

Enclosure 13.5 Pzr Relief Valve Leakage Calculation

3. Unit 2 Pzr Steam Space Leakage Excel Calculation available PT/21 A/060010 1 0 Page 2 of9 3.1 Use Unit 2 Pzr Stearn Space Leakage Excel Calculation to determine leakage: Unit 2 Pzr Steam Space Leakage = _________

gpm 3.2 Perform the following to determine SSF ASW System operability:

{II}

• Refer to Autolog or contact I&E to determine operable SSF Pzr Heaters.

• Refer to TS Bases 3.10.1 to determine required Pzr heaterslPzr leakage. 3.3 IF SSF ASW System is inoperable due to excessive stearn space leakage, perform the following:

3.3.1 EnterTS

3.10.1 Condition

'A' for SSF ASW System inoperability.

3.3.2 IF required, notify SPOC to restore Pzr Heaters per IP/O/B/02001037 (Pressurizer Heater Test and Surveillance).

3.3.3 Notify

System Duty Engineer.

3.4 Record

Unit 2 Pzr Stearn Space Leakage in Autolog.

Enclosure 13.5 Pzr Relief Valve Leakage Calculation

4. Example Of Rep Seal Leakage Flow Trend History ** HISTORY ** GROUP TREND ** HISTORY ** 4.0 3.5 3.0 2.0 1.5 1.0 0.5 0.0 11 :37:25:63 11 :39:36:93 11:41 :52:23 11 :44:05:53 PT 121 Al0600lO 1 0 Page 3 of9 Seal leakage flow r2.tcw rtr 8104/05 Rep SEAL LEAKAGE FLOW Enclosure 13.5 Pzr Relief Valve Leakage Calculation PT 121 A/0600/0 1 0 Page 4 of9 5. Unit 2 Pzr Steam Space Leakage Excel Calculation NOT available

{IS} 5.1 Perform of the following to obtain 2A1 RCP Seal Leakage Flow: IF 2A1 RCP Seal Leakage Flow (CP 02A1938) 2 0.30 gpm, record indicated value below and in Step 5.5: 2A1 RCP Seal Leakage Flow: ______ gpm IF 2A1 RCP Seal Leakage Flow (CP 02A1938) < 0.30 gpm AND Time Trend/History for 2A1 RCP Seal Leakage Flow (CP 02A1938) indicates

< 2 dumps in the past hour, record 0.0 gpm for 2A1 RCP Seal Leakage Flow in Step 5.5: 2Al RCP Seal Leakage Flow: __

gpm

• IF 2Al RCP Seal Leakage Flow (CP 02A1938) < 0.30 gpm AND Time Trend/History for 2Al RCP Seal Leakage Flow (CP 02A1938) indicates 2 2 dumps in the past hour, perform the following:

A. Calculate flow rate using Time TrendlHistory: 1. Record Time #1 2A1 RCP Seal Leakage Flow (CP 02A1938):

04:

00 HH:MM:SS 2. Record Time #2 2A1 RCP Seal Leakage Flow: (CP 02A1938):

Olf.2':CO HH:MM:SS 3. Record Time # 1 to Time #2 Duration:

II 40 Calculate 2Al RCP Seal Leakage Flow: (0.29 + l J 40 sec)(60) = O. 0 I (Duration)

(2Al Rep Seal Leakage Flow) Record indicated value below and in Step 5.5: 2A1 RCP Seal Leakage Flow: O. 0 I gpm seconds gpm Enclosure 13.5 Pzr Relief Valve Leakage Calculation PT 121 Al060010 1 0 Page 5 of9 5.2 ;:J0rm.!!.ill:

of the following to obtain 2A2 RCP Seal Leakage Flow: /I/}/I-IF 2A2 RCP Seal Leakage Flow (CP 02A1940) 0.30 gpm, record indicated value below and in Step 5.5: 2A2 RCP Seal Leakage Flow: ______ gpm IF 2A2 RCP Seal Leakage Flow (CP 02Al940) < 0.30 gpm AND Time Trend/History for 2A2 RCP Seal Leakage Flow (CP 02Al940) indicates

< 2 dumps in the past hour, record 0.0 gpm for 2A2 RCP Seal Leakage Flow in Step 5.5: 2A2 RCP Seal Leakage Flow: __

gpm -IF 2A2 RCP Seal Leakage Flow (CP 02Al940) < 0.30 gpm AND Time Trend/History for 2A2 RCP Seal Leakage Flow (CP 02A1940) indicates 2 dumps in the past hour, perform the following:

A. Calculate flow rate using Time Trend/History:

rpJ 1. Record Time #1 2A2 RCP Seal Leakage Flow (CP 02A I 940): 04: 00:00 HH:MM:SS 2. Record Time #2 2A2 RCP Seal Leakage Flow: (CP 02Al940):

Olf: OJ: lf9 HH:MM:SS Record Time #1 to Time #2 Duration:

_ ..... l'-'O""--9-L--

____ seconds 4. Calculate 2A2 RCP Seal Leakage Flow: ) (0.29+ loG) (Duration) sec)(60) = (). L to (2A2 Rep Seal Leakage Flow) Record indicated value below and in Step 5.5: 2A2 RCP Seal Leakage Flow: O. l to gpm gpm Enclosure 13.5 Pzr Relief Valve Leakage Calculation PT 121 A/060010 1 0 Page 6 of9 Perform of the following to obtain 2BI RCP Seal Leakage Flow: AYiA. IF 2Bl RCP Seal Leakage Flow (CP 02A1939) 0.30 gpm, record indicated value below and in Step 5.5: 2B 1 RCP Seal Leakage Flow: ______ gpm IF 2Bl RCP Seal Leakage Flow (CP 02A1939) < 0.30 gpm AND Time Trend/History for 2Bl RCP Seal Leakage Flow (CP 02A1939) indicates < 2 dumps in the past hour, record 0.0 gpm for 2Bl RCP Seal Leakage Flow in Step 5.5: 2B 1 RCP Seal Leakage Flow: __ ..;;.0..;.;.0;;...-._

gpm

• IF 2Bl RCP Seal Leakage Flow (CP 02A1939) < 0.30 gpm AND Time Trend/History for 2Bl RCP Seal Leakage Flow (CP 02A1939) indicates 2 dumps in the past hour, perform the following:

A. Calculate flow rate using Time Trend/History: 1. Record Time #1 2BI RCP Seal Leakage Flow (CP 02AI939): 1h!. OU:oO:oD HH:MM:SS Record Time #2 2BI RCP Seal Leakage Flow: (CP 02A1939):

oLr.\4:30 HH:MM:SS Record Time #1 to Time #2 Duration:

_--=f?_I-'--"O=--

___ seconds Calculate 2B 1 RCP Seal Leakage Flow: (0.29 + 70 sec) (60) = O* 0 "2-gpm (Duration)

(2BI Rep Seal Leakage Flow) Record indicated value below and in Step 5.5: 2B 1 RCP Seal Leakage Flow: O. Q:L gpm Enclosure 13.5 Pzr Relief Valve Leakage Calculation PT 121 Al0600/0 1 0 Page 7 of9 5.4 Perform of the following to obtain 2B2 RCP Seal Leakage Flow: M. IF 2B2 RCP Seal Leakage Flow (CP 02A194l) 0.30 gpm, record indicated value below and in Step 5.5: di. 2B2 RCP Seal Leakage Flow: ______ gpm IF 2B2 RCP Seal Leakage Flow (CP 02Al941) < 0.30 gpm AND Time Trend/History for 2B2 RCP Seal Leakage Flow (CP 02Al941) indicates

< 2 dumps in the past hour, record 0.0 gpm for 2B2 RCP Seal Leakage Flow in Step 5.5: 2B2 RCP Seal Leakage Flow: __ ..;;.0,;..;.0:...-_

gpm

• IF 2B2 RCP Seal Leakage Flow (CP 02A1941) < 0.30 gpm AND Time Trend/History for 2B2 RCP Seal Leakage Flow (CP 02A1941) indicates 2 dumps in the past hour, perform the following:

A. Calculate flow rate using Time Trend/History:

¥ 1. Record Time #1 2B2 RCP Seal Leakage Flow (CP 02AI94l):

HH:MM:SS 2. Record Time #2 2B2 RCP Seal Leakage Flow: (CP 02AI941):

HH:MM:SS Record Time # 1 to Time #2 Duration:

Ll ::3 5 seconds --------Calculate 2B2 RCP Seal Leakage Flow: (0.29+ 4'6S sec)(60)=

O.oLl (Duration)

(2B2 Rep Seal Leakage Flow) Record indicated value below and in Step 5.5: 2B2 RCP Seal Leakage Flow: D. 0 4 gpm gpm

¥-5.5 5.6 Enclosure 13.5 Pzr Relief Valve Leakage Calculation PT 121 Al060010 1 0 Page 8 of9 Sum individual RCP Seal Leakage Flows to determine Total RCP Seal Leakage Flow: 2AI RCP Seal Leakage Flow: 0.01 gpm 2A2 RCP Seal Leakage Flow: o. lio gpm 2B 1 RCP Seal Leakage Flow:

gpm 2B2 RCP Seal Leakage Flow: O. 0 4-gpm Total RCP Seal Leakage Flow: 0.23 gpm Perform the following to obtain Pzr Relief Valve Leak Rate: 5.6.1 Determine Quench Tank (QT) level change: (Final QT level) (Initial QT level) (QT level Change) 5.6.2 Convert QT Level Change to gallons: {4} _______ inches x 34.94 galslinch

= gals (QT Level Change) (QT Volume Change) 5.6.3 Calculate QT Volume Change Rate: _______ gals + ____ mIll = gpm (QT Volume Change) (Duration) (QT Volume Rate) 5.7 Calculate Pzr Steam Space Leakage: ______ gpm -gpm = gpm (QT Volume Rate) (Total RCP Seal Leakage Flow) (pzr Steam Space leakage) 5.8 Determine SSF ASW Pump operability:

{II}

• Refer to Autolog or contact I&E to determine operable SSF Pzr Heaters.

• Refer to TS Bases 3.10.1 to determine required Pzr heaters/pzr leakage.

Enclosure 13.5 Pzr Relief Valve Leakage Calculation PT 121 Al060010 1 0 Page 9 of9 5.9 IF SSF ASW System is inoperable due to excessive steam space leakage, perform the following:

• Enter TS 3.10.1 Condition

'A' for SSF ASW System inoperability.

• IF required, notify SPOC to restore Pzr Heaters per IP/O/BI02001037 (Pressurizer Heater Test and Surveillance).

• Notify System Duty Engineer.

5.10 Record Unit 2 Pzr Steam Space Leakage in Autolog.

Enclosure 13.5 Pzr Relief Valve Leakage Calculation PT 121 A/0600/o 1 0 Page 8 of9 2L-5.5 Sum individual RCP Seal Leakage Flows to detennine Total RCP Seal Leakage Flow: 2A 1 RCP Seal Leakage Flow: 0.0 l gpm 2A2 RCP Seal Leakage Flow: C). I to gpm 2B 1 RCP Seal Leakage Flow:

gpm 2B2 RCP Seal Leakage Flow: ",6f gpm Total RCP Seal Leakage Flow: O,}3 gpm 5.6 Perform the following to obtain Pzr Relief Valve Leak Rate: L 5.6.1 Determine Quench Tank (QT) level change: 0 (Final QT level) (Initial QT level) (QT level Change) L5.6.2 Convert QT Level Change to gallons: {4}

inches x 34.94 galslinch

= 4. if S &> gals (QT Level Change) (QT Volume Change) 5.6.3 Calculate QT Volume Change Rate:

gals + '0 min = O*l{ f gpm (QT Volume Change) (Duration) (QT Volume Rate) L5.7 Calculate Pzr Steam Space Leakage: 6 r 41 gpm -0 I f3 gpm = 0 . I A gpm (QT Volume Rate) (Total RCP Seal Leakage Flow) (pzr Steam Space leakage) 5.8 Determine SSF ASW Pump operability:

{II}

• Refer to Autolog or contact I&E to determine operable SSF Pzr Heaters.

• Refer to TS Bases 3.10.1 to detennine required Pzr heaters/pzr leakage.

CANDIDATE EXAMINER REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-203 Sf2D OAJtf Complete Plant Configuration Sheet (Time to Core Boil) Admin-203 fnl Page 1 of 7 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Complete Plant Configuration Sheet (Time to Core Boil) Alternate Path: No Facility JPM #: Admin 203 KIA Rating(s):

System: GEN KIA: 2.2.18 Rating: 2.6/3.9 Task Standard:

Admin-203 fnl Page 2 of 7 Tables in OP/O/A/1108/001 are used to determine Total Loss Of DHR Time to Boil Preferred Evaluation Location:

Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate

References:

OP/O/A/1108/001 (Curves and General Information)

Enclosure 4.46 (Total Loss of DHR Time to Boil) Validation Time: 11 minutes Time Critical:

NO ====================================================================================

Candidate:

Time Start: ___ _ NAME Time Finish: ___ _ Performance Rating: SAT ___ UNSAT __ _ Performance Time: ----Examiner:

______

NAME SIGNATURE DATE ====================================================================================

COMMENTS SIMULATOR OPERATOR INSTRUCTIONS:

NONE Admin-203 fnl Page 3 of 7 Tools/Equipment/Procedures Needed: Admin-203 fnl Page 4 of 7 OP/0/A/1108/001 (Curves and General Information)

Enclosure 4.46 (Total Loss of DHR Time to Boil) 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 was shutdown on12/01 0400

• Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2.A is being prepared for this shift. INITIATING CUES: Current Date/Time:

12/04 0600 The SRO instructs you to calculate the "Time To Core Boil" and perform any required actions based on the calculation results in accordance with Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2.A.

STARTTIME:

__ _ STEP 1: Refer to enclosure 4.46 of OP/0/Al110S/001 Choose the appropriate table STANDARD:

Refer to enclosure 4.46 of OP/O/Al11 OS/001 and use the "Prior to Refueling

-Initial Temp = 110°F (Hours Since SID); Time to Boil in Minutes" table. COMMENTS:

STEP 2: Determine the number of hours the reactor has been shutdown.

STANDARD:

Determine the reactor has been shut down for 74 Hours. COMMENTS:

STEP 3: Determine time to boil. STANDARD:

Determine time to boil is 20.9 minutes by using 74 hours3.083 days <br />0.44 weeks <br />0.101 months <br /> and SO inches on L T-5. COMMENTS:

STEP 4: Ensure SPOC is manning equipment hatch STANDARD:

Ensures SPOC is manning equipment hatch since Configuration Sheet indicates that Equipment Hatch is Open COMMENTS:

END TASK STOP TIME: ____ _ Admin-203 fnl Page 5 of 7 CRITICAL STEP SAT -UNSAT -CRITICAL STEP SAT -UNSAT -CRITICAL STEP SAT -UNSAT -SAT -UNSAT -

CRITICAL STEP EXPLANATIONS:

STEP # Explanation 1 Required to determine the time for core boil. 2 Required to determine the time for core boil. 3 Required to determine the time for core boil. Admin-203 fnl Page 6 of 7 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS:

• Unit 1 was shutdown on12/01 0400 Admin-203 fnl Page 7 of 7

• Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.3.A is being prepared for this shift. INITIATING CUES: Current Date/Time:

12/040600 The SRO instructs you to calculate the "Time To Core Boil" and perform any required actions based on the calculation results in accordance with Site Directive 1.3.5 (Shutdown Protection Plan) Attachment 9.2.A.

Attachment 9.2.A -Plant Configuration Sheet Unit 1 Mode: 6 Preparer:

Date: TODAY Time: 4:00 Reviewer:

Date: Time: RCS Level: 80 in. As Read On: LT-5 RCS Temperature:

110 of As Read On: LPIP Suction RCS Level Control Band: 84 in. (High) 62 in. (Low) RCS Temperature Band: 125 of (High) 90 of (Low) LPI Pumps Operable:

A W B W C W LPSW Pumps Operable A W B W C W LPI Pumps Coolers: A W B W LPSW Suction From Unit: 2 CCW SF Pumps Operable:

A W B W C W RCW Pumps Available:

A W B W C W D W SF Coolers Operable:

A W B W C W RCW Coolers Available A W B W C W D W SFP Level: 0.18 ft. SFP Temperature 71 of Level Control Band: -2 ft. To 1 ft. Time For SFP Temperature to Reach 210°F: >66 hours2.75 days <br />0.393 weeks <br />0.0904 months <br /> FTC Flooded YES r NO W Reactor Vessel Head OFF r ON W Fuel in Reactor Vessel YES W NO r r'am AvaliaOle (t-Iange on wi YES W NO r No Red Tags on LP-19) Operable CETCs SOME List: G6, F7, F8, H9, G11 Lr'-,W :sump r'atn Available

(!-Iange ott wi YES r NO W No Red Tags on LP-20) Time To Core Boil Minutes Reactor Bldg Purge is: OFF W ON r If Time to Core Boil is 16 min. ensure equipment hatch is closed. Equipment Hatch is: CLOSED I OPEN W If Time to Core Boil is < 30 min. ensure is manning equip. hatch if open. SPOC is manning Equip. Hatch: YES r NO r RCS Makeup Paths AOTSG BOTSG W BHUT --> HP-363 --> A / B LPI ABHUT 57,071 GAL. Upper Primary Handholes ON W OFF I ON W OFF r w BWST --> A / B LPI (Forced / Gravity) BWST 377,146 GAL. Upper Primary Manways ON W OFF r ON w OFF r w BWST / BHUT --> A HPI --> HP-410 CBAST 4,770 GAL. YES r NO r YES r NO w I BWST / BHUT --> B HPI --> HP-409 OTSG Nozzle Dam Installed RCS Boron: 2750 (Actual) 675 (Required)

Cold Legs Are: DRAINED r NOT DRAINED W* Canal Seal Plate: ON W OFF r SF-1 OPEN r CLOSED W Transfer Tube Covers ON W OFF r SF-2 OPEN r CLOSED W OFFSITE POWER SOURCES Main Feeder Bus # 1 Energized YES W NO r CT-1 I CT-2 r CT-3 I BACKCHARGED MAIN TRANSFORMER W Main Feeder Bus # 2 Energized YES W NO r CT-5 (From Central Switchyard)

W EMERGENCY POWER SOURCES CT-1 W CT-2 r CT-3 r RC-66 Installed on PZR YES r NO w CT-4 W RC-67 Installed on PZR YES r NO w CT-5 (From Lee Combustion Turbine via Isolated Power Path) I RC-68 Installed on PZR YES r NO W NOTES:

Attachment 9.2.A -Plant Configuration Sheet Unit 1 Mode: 6 Preparer:

Date: TODAY Time: 4:00 Reviewer:

Date: Time: RCS Level: 80 in. As Read On: LT-5 RCS Temperature:

110 of As Read On: LPIP Suction RCS Level Control Band: 84 in. (High) 62 in. (Low) RCS Temperature Band: 125 of (High) 90 of (Low) LPI Pumps Operable:

A Fl B j7 C j7 LPSW Pumps Operable A j7 B j.;i C P LPI Pumps Coolers: A pc B R LPSW Suction From Unit: 2 CCW SF Pumps Operable:

A R: B W C RCW Pumps Available:

A W B W C f;1 D P SF Coolers Operable:

A R: B W C R RCW Coolers Available A W B j'" C W D W SFP Level: 0.18 ft. SFP Temperature 71°F Level Control Band: -2 ft. To 1 ft. Time For SFP Temperature to Reach 210 OF: >66 hours2.75 days <br />0.393 weeks <br />0.0904 months <br /> FTC Flooded YES r: NO W Reactor Vessel Head OFF r ON R Fuel in Reactor Vessel YES j7 NO r t-'arn AvaliaOle(t"lange Oil WI YES W NO r-Na Red Tags on LP-19) j Operable CETCs SOME List: G6, F7, F8, H9, G11 Lt-'-lU t-'arn AvallaOle (t"lange all wI No Red Tags on LP-20) YES r NO I'" Time To Core Boil Minutes Reactor Bldg Purge is: OFF W ON r-If Time to Core Boil is 16 min. ensure equipment hatch is closed. Equipment Hatch is: CLOSED r OPEN W If Time to Core Boil is < 30 min. ensure is manning equip. hatch if open. SPOC is manning Equip. Hatch: YES r--NO r RCS Makeup Paths AOTSG BOTSG v BHUT --> HP-363 --> A I B LPI ABHUT 57,071 GAL. Upper Primary Handholes ON [.;;' OFF ON P' OFF r r--W BWST --> A I B LPI (Forced I Gravity) BWST 377,146 GAL. Upper Primary Manways ON p; OFF r ON W OFF ! r;t BWST I BHUT --> A HPI--> HP-410 CBAST 4,770 GAL. YES NO YES r NO 1"'-r BWST I BHUT -> B HPI--> HP-409 OTSG Nozzle Dam Installed RCS Boron: 2750 (Actual) 675 (Required)

Cold Legs Are: DRAINED r NOT DRAINED W' Canal Seal Plate: ON R OFF r SF-1 OPEN r CLOSED W Transfer Tube Covers ON R" OFF r SF-2 OPEN r CLOSED R , OFFSITE POWER SOURCES Main Feeder Bus # 1 Energized YES 57 NO r CT-1 C CT-2 CT-3 I"""' t ... , BACKCHARGED MAIN TRANSFORMER P Main Feeder Bus # 2 Energized YES po NO r CT-5 (From Central Switchyard)

R EMERGENCY POWER SOURCES CT-1 pc CT-2 r: CT-3 r RC-66 Installed on PZR YES r NO P' CT-4 j7 RC-67 Installed on PZR YES r NO w CT-5 (From Lee Combustion Turbine via Isolated Power Path) r RC-68 Installed on PZR YES r NO R" NOTES:

REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE fGO O,u L 1 Admin-207 Admin-207 fnl Page 1 of 9 Perform SG Downcomer Temperature Surveillance CANDIDATE EXAMINER Task: REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Perform SG Downcomer Temperature Surveillance Alternate Path: No Facility JPM #: New KIA Rating(s):

System: Gen KIA: 2.2.12 Rating: 3.7/4.1 Task Standard:

Admin-207 fnl Page 2 of 9 Perform SG Downcomer Temperature Surveillance by procedure for the 1A (and ONLY the 1A) SG and determine that the surveillance is NOT met. Preferred Evaluation Location:

Preferred Evaluation Method: Simulator

_X_ In-Plant __ Perform X Simulate

References:

OP/1/A/11 05/014 Encl 4.1 (Mode 1 &2) and Enc!. 4.16 (Channel Check Of OTSG Downcomer Temperatures)

Validation Time: 18 minutes Time Critical:

NO ====================================================================================

Candidate:

Time Start: ----NAME Time Finish: __ _ Performance Rating: SAT ___ UNSAT __ _ Performance Time: ----Examiner:

________________________

_ NAME SIGNATURE DATE ====================================================================================

COMMENTS SIMULATOR OPERATOR INSTRUCTIONS INITIAL SETUP 1. Recall SNAP 212 2. Import files for Admin 207 3. Briefly place simulator in RUN then return to FREEZE SUBSEQUENT SETUP Admin-207 fnl Page 3 of 9 It is NOT necessary to recall simulator between JPM's. Simulator can remain in freeze and only actions below are required.

1. Call up different OAC screens than ones required during the JPM Tools/Equipment/Procedures Needed: OP/1/A/1105/014 (Control Room Instrumentation Operation And Information)

READ TO OPERATOR DIRECTION TO TRAINEE: Admin-207 fnl Page 4 of 9 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 = 100% OP/1/A/11 05/014 (Control Room Instrumentation Operation And Information)

Enclosure 4.1 (Mode 1 & 2) in progress.

INITIATING CUES: CR SRO directs you to continue OP/1/A/11 05/014 (Control Room Instrumentation Operation And Information)

Enclosure 4.1 (Mode 1 & 2) beginning on page 4.

START TIME: __ _ STEP 1: Verify All SG Downcomer Temperature computer pOints agree within 3°F of each other. IF All SG Downcomer Temperatures DO NOT agree within 3°F of each other, then perform Enclosure "Channel Check Of OTSG Downcomer Temperatures".

01 E2008 -535.4 OF 01 E2009 -541.3°F 01E2012 -535.4°F 01 E2013 -535.4 OF STANDARD:

Determine that the above OAC point do NOT agree within 3°F of each other, and perform Enclosure "Channel Check Of OTSG Downcomer Temperatures".

COMMENTS:

STEP 2: Step 3.1 Determine saturation temperature for 1 A OTSG based on power level and 1 A OTSG outlet pressure as follows: Step 3.1.1 Determine 1A OTSG outlet pressure using anyone of the following computer points:

• 01 E2281 -892.4 psig

• 01 E2283 -892.4 psig

• 01 E2031 -892.4 psig

• 01 E2032 -892.4 psig STANDARD:

Using the OAC determine that 1A OTSG pressure is 892 psig. COMMENTS:

Admin-207 fnl Page 5 of 9 CRITICAL STEP SAT -UNSAT -SAT -UNSAT -

Admin-207 fnl age 0 P 6 f9 STEP 3: Step 3.1.2 Using table in Section 4, determine the 1 A OTSG saturation temperature SAT based on power level and 1 A OTSG Outlet Pressure obtained in step -3.1.1. 1A OTSG saturation temperature UNSAT -STANDARD:

Determine that 1A OTSG saturation temperature is "" 535.4°F by using the table iN section 4. COMMENTS:

STEP 4: Step 3.1.3 Compare 01 E2008 SG Lower Downcomer Temperature Loop A to the SAT 1 A OTSG saturation temperature determined in step 3.1.2: -STANDARD:

Determine that 01 E2008 SG Lower Downcomer Temperature Loop A is approximately the same as the 1 A OTSG saturation temperature above. -UNSAT COMMENTS:

STEP 5: Step 3.1.4 IF 01 E2008 SG Lower Downcomer Temperature Loop A is NOT within SAT +/- 4.9 of of the 1 A OTSG saturation temperature, then enter Condition A -of SLC 16.7.5 for OTSG overfill protection system inoperable.

STANDARD:

Determine that 01 E2008 SG Lower Downcomer Temperature Loop A is UNSAT within +/- 4.9 of of the 1A OTSG saturation temperature and N/A this step. -COMMENTS:

Admin-207 fnl P f9 age 70 STEP 6: Step 3.1.5 CRITICAL STEP Compare 01 E2009 SG Lower Downcomer Temperature Loop A to the SAT 1 A OTSG saturation temperature determined in step 3.1.2: -STANDARD:

Determine that 01 E2009 SG Lower Downcomer Temperature Loop A is approximately 6°F above 1 A OTSG saturation temperature above UNSAT -COMMENTS:

STEP 7: Step 3.1.6 CRITICAL STEP IF 01 E2009 SG Lower Downcomer Temperature Loop A is NOT within SAT +/- 4.9 of of the 1 A OTSG saturation temperature, then enter Condition A -of SLC 16.7.5 for OTSG overfill protection system inoperable.

STANDARD:

Determine that 01 E2009 SG Lower Downcomer Temperature Loop A is UNSAT NOT within +/- 4.9 of of the 1A OTSG saturation temperature, and enter -Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable.

Cue: SRO is notified to enter SLC 16.7.5 Condition A and another operator will complete this procedure COMMENTS:

END TASK STOP TIME: ____ _

CRITICAL STEP EXPLANATIONS:

STEP # Explanation 1 Step is required to complete the surveillance.

6 Step is required to complete the surveillance.

7 Step is required to determine that entry into SLC 16.7.5 is required.

Admin-207 fnl Page 8 of 9 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS:

Reactor power = 100% Admin-207 fnl Page 9 of 9 OP/1/A/11 05/014 (Control Room Instrumentation Operation And Information)

Enclosure 4.1 (Mode 1 & 2) in progress.

INITIATING CUES: CR SRO directs you to continue OP/1/A/11 05/014 (Control Room Instrumentation Operation And Information)

Enclosure 4.1 (Mode 1 & 2) beginning on page 4.

Enclosure 4.16 Channel Check Of OTSG Downcomer Temperatures opil IAI 1 1051014 Page 1 of3 1. Limits And Precautions None 2. Initial Conditions 2.1 OTSG in service. 3. Procedure NOTE: Interpolation of the chart may be necessary for different power levels and OTSG outlet pressures.

3.1 Determine

saturation temperature for lA OTSG based on power level and lA OTSG -outlet pressure as follows: SiS-1 3.1.1 0f-T 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6 Determine lA OTSG outlet pressure using anyone of the following computer points:

• 01E2281

• 01E2283

• 01E203l

• 01E2032 Using table in Section 4, determine the lA OTSG saturation temperature based on power level and lA OTSG Outlet Pressure obtained in step 3.1.1. 1 A OTSG saturation temperature Compare 01E2008 SG Lower Downcomer Temperature Loop A to the lA OTSG saturation temperature determined in step 3.1.2: IF 01E2008 SG Lower Downcomer Temperature Loop A is NOT within +/- 4.9 of of the lA OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable.

Compare 01E2009 SG Lower Downcomer Temperature Loop A to the 1A OTSG saturation temperature determined in step 3.1.2: IF 01E2009 SG Lower Downcomer Temperature Loop A is NOT within +/- 4.9 of of the 1A OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable.

Enclosure 4.16 Channel Check Of OTSG Downcomer Temperatures OP!l/A/I1051014 Page 2 of3 NOTE: Interpolation of the chart may be necessary for different power levels and OTSG outlet pressures.

3.2 Determine

saturation temperature for 1 B OTSG based on power level and 1 B OTSG outlet pressure as follows:

M" 3.2.1 s*s;') 322 .. s 3 2 3 cl.L ..

3.2.4 oTf 3.2.5 Determine IB OTSG outlet pressure using anyone of the following computer points:

• 01E2282

• 01E2284 Using table in Section 4, determine the IB OTSG saturation temperature based on power level and IB OTSG Outlet Pressure obtained in step 3.2.1. IB OTSG saturation temperature Compare 01E2012 SG Lower Downcomer Temperature Loop B to the IB OTSG saturation temperature determined in step 3.2.2: IF 01E2012 SG Lower Downcomer Temperature Loop B is NOT within +/- 4.9 of of the IB OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable.

Compare OlE2013 SG Lower Downcomer Temperature Loop B to the IB OTSG saturation temperature determined in step 3.2.2: IF OlE2013 SG Lower Downcomer Temperature Loop B is NOT within +/- 4.9 of of the IB OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable.

Enclosure 4.16 Channel Check Of OTSG Downcomer Temperatures OP/IIAlI105/014 Page 3 of3 4. OTSG Lower Downcomer Saturation Temperature eF) As A Function Of Power Level And OTSG Outlet Pressure NOTE: Interpolation of the chart may be necessary for different power levels and OTSG outlet pressures.

Power OTSG Outlet Pressure (psig) Level (%) 860 870 880 890 900 910 920 15 529.l 530.4 531.7 533.0 534.3 535.6 536.9 25 529.2 530.5 531.8 533.1 534.4 535.7 537.0 35 529.3 530.6 531.9 533.2 534.5 535.8 537.1 50 529.5 530.9 532.2 533.5 534.8 536.1 537.4 65 529.9 531.2 532.5 533.9 535.1 536.4 537.7 75 530.2 531.5 532.8 534.1 535.4 536.7 538.0 85 530.6 531.9 533.2 534.5 535.8 537.0 538.3 95 530.9 532.3 533.6 534.9 536.1 537.4 538.7 100 531.2 532.5 533.8 535.1 536.4 537.6 538.9 CANDIDATE EXAMINER REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE 6r2o ADMIN-303 STAY TIME CALCULATION Admin-303 fnl Page 1 of 7 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Determine stay time for an activity Alternate Path: No Facility JPM #: Admin 303 KIA Rating(s):

System: GEN KIA: 2.3.7 Rating: 3.5/3.6 Task Standard:

Admin-303 fnl Page 2 of 7 Correctly determine that total dose received for the job is 16.7 mR and maximum clock time to complete venting without exceeding RWP dose limits is 18.5 minutes (18.0 -19.0 is acceptable).

Preferred Evaluation Location:

Preferred Evaluation Method: Simulator In-Plant __ Perform X Simulate

References:

NSD-507, Radiation Protection Validation Time: 13 minutes Time Critical:

NO ====================================================================================

Candidate:

Time Start: ----NAME Time Finish: __ _ Performance Rating: SAT ___ UNSAT __ _ Performance Time: ----Examiner:

______________

---

NAME SIGNATURE DATE ====================================================================================

COMMENTS SIMULATOR OPERATOR INSTRUCTIONS:

None Admin-303 fnl Page 3 of 7 Tools/Equipment/Procedures Needed: Radiation Work Permit # 23 Survey Map READ TO OPERATOR DIRECTION TO TRAINEE: Admin-303 fnl Page 4 of 7 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 in AP/26, Loss of Decay Heat Removal and you are to:

• Stage yourself inside Room 61 where you can minimize your dose while waiting

• Vent 1A LPI pump when directed Room 61 is posted: High Radiation Area 0800 -You enter Room 61 0830 -You are directed to vent 1A LPI pump 0842 -Venting is completed.

You immediately exit the Room and report back to the Control Room. INITIATING CUES: Based on the time line, RWP 23, and Room 61 survey map provided:

1. State the amount of dose that was received for the duration of this task. 2. Assuming you entered the room and began venting at the previously stated times, determine the maximum time that you could vent the pump without exceeding a limit imposed by the RWP.

STARTTIME:

__ _ STEP 1: What dose will be received for the duration of this task? Based on a 30 minute wait at the LEWA and 12 minutes at LPI Pump and the nearest posted general area dose rates (12 mr/hr): LEWAdose:

Vent time dose Area dose is 3 mr/hr X 0.5 hr = 1.5 mR 12/60 hr X 76 mr/hr = 15.2 mR Estimated total dose received is 1.5 + 15.2= 16.7 mR NOTE: Acceptable range is 16.5 mR to 17.2 mR STANDARD:

Calculates the dose received for the duration of the task. COMMENTS:

STEP 2: What is the maximum time that the pump casing could have been vented before reaching a limit imposed by the RWP? Based on the nearest general area dose rates (76 mr/hr): The RWP Dose Alarm is 25 mR. LEWA is 3 mr/hr X 0.5 hr = 1.5 mR Vent time dose rate is Rad level = 76 mr/hr Solving: 23.5 mr is allowable dose once venting starts 23.5 mr = 0.309 hours12.875 days <br />1.839 weeks <br />0.423 months <br /> or 18.5 minutes 76 mr/hr Note: Acceptable range is 18.0 -19.0 minutes. STANDARD:

Calculates maximum venting time. COMMENTS:

END TASK STOP TIME: ____ _ Admin-303 fnl Page 5 of 7 CRITICAL STEP SAT UNSAT CRITICAL STEP SAT UNSAT CRITICAL STEP EXPLANATIONS:

STEP # Explanation 1 Required to calculate dose received while performing task. 2 Required to calculate the maximum venting time. Admin-303 fnl Page 6 of 7 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) 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 in AP/26, Loss of Decay Heat Removal and you are to:

• Stage yourself inside Room 61 where you can minimize your dose while waiting

• Vent 1A LPI pump when directed Room 61 is posted: High Radiation Area 0800 -You enter Room 61 0830 -You are directed to vent 1A LPI pump 0842 -Venting is completed.

You immediately exit the Room and report back to the Control Room. INITIATING CUES: Based on the time line, RWP 23, and Room 61 survey map provided:

1. State the amount of dose that was received for the duration of this task. 2. Assuming you entered the room and began venting at the previously stated times, determine the maximum time that you could vent the pump without exceeding a limit imposed by the RWP.

Room 61 LPI & RBS Pumps Survey # M-021506-17 d DatelTime 03/26/2010 13:06 ENTIRE ROOM CONTAMINATED Comments:

PLANVIEW UPDATED TO SHOW ENTIRE ROOM CONTAMINATED FOR RECOATING PROJECT. ALL DOSE RATE INFO. FROM PREVIOUS SURVEY M-020706-2 Type: Job Coverage RWP: 5036 Reactor Power = 100% Dose Rate I HS¥50 I Hot Spot till=150 Contact Reading __ +75 30 em Reading Posting 20 General Area DripBag @ Smear M\ Air Sample Wipe Unless otherwise noted, dose rates in mrem/hr. Surveyor:

W. Walters Summary of Highest Readings Smears Air Samples & Wipes 1) 2554 DPM/100 cm2 [3Iy Approved by: N. Wriston, 03/27/2010 Training Use Only Oconee Nuclear Station Radiation Work Permit Training Use Only Entry For Routine Plant And Systems Operation RWP#23 . Rev: 27 Task # 1 Ent for Routine Plant and S ED Alarm Set Points: Dose Alarm: 10 Dose Rate Alarm: 50 Stay Time Alarm: 55:00 RWP Requirements Dress Category/Work Description

• Dress Category "A" Work in a non-contaminated area

• Dress Category "B" Work in a non-contaminated area with contaminated material where there is NO potential for contact with

• Dress Category "C" Work in a non-contaminated area with contaminated material where there is NO potential for contact with

• Dress Category "D" Work of short duration, in open area(s) with NO obstructions that could contribute to contamination of unprotected

• Dress Category "E" Work where: (1) Complete protection of skin and clothing is NOT required; (2) Durability of surgical gloves requires

• Dress Category "F" Work in a contaminated area where complete protection of skin and clothing is NOT necessary.

• Dress Category "G" Work in a dry contaminated area.

• Dress Category "H" Work in a contaminated area.

• Dress Category "I" Hands on work with higher contaminated material or beta dose concerns to hands only.

• Dress Category "N" Performing work in contaminated wet conditions.

• Modesty garments, top & bottom, are required under protective clothing where personal outer clothing is not worn Contamination Control

• Change outer rubber gloves often when handling highly contaminated material as directed by RP

• If installing a drain rig, secure hose OR tubing to floor drain

• If installing a drain rig, use hose clamps or similar device to secure hose OR tubing connections

• Install catch containments OR drain rigs to prevent spills if draining components

• Use surgical gloves in lieu of rubber gloves for the manipulation of small or specialty items as directed by RP

• Utilize facial protection (e.g. face shield, hood sock, power visor) as directed by RP

• Wear disposable (plastic) booties inside of orex booties for work in wet conditions

• Wipe down AND bag all tools and equipment prior to removal from a contaminated area as directed by RP RP Job Coverage

• Pre-job briefing required

• Start of Job, Intermittent or No Coverage for work in High Radiation Areas or less

• Timekeeping/dose controller required for workers exposed to an actual dose rate >1500 mrem/hr OR dose will exceed 500 mrem for an individual entry Dosimetry Requirements

• 1. High noise level in the work area.

• 2. Use of head phones

• 3. Hearing impairment

• 4. Any other condition that would impair hearing an ED alarm

• An Auxiliary ED alarm is required in areas where general area dose rates are> 100 mrem/hr if any of the following conditions exist:

• Monitor ED periodically while inside the RCNRCZ (once or twice per hour in low dose rate areas). Monitor more frequently in higher dose Respiratory Protection

• If weighted DAC-Hours are expected to result in greater than or equal to 4 DAC-Hours per person, perform a TEDE/ALARA evaluation Approved on 11/12/2009 by ROBINSON, LAGRONE D Printed on 02/10/2010 Activated on 11/1212009

• Full Face Particulate (Additional Hood Required)

IF warranted by TEDE ALARA Evaluation OR directed by RP RP Hold Points

• Accumulated dose higher than expected

• Notify RP prior to reaching OR entry into the overhead (8 feet and above)

• Notify RP Prior to Start of Work

• RP briefing required prior to entering High Radiation Areas

• RP survey required prior to handling debris or foreign material

• RP survey required prior to handling valve/pump parts or intemals Stop Work Criteria

• Actual contamination levels are higher than the expected levels written on this RWP task

• Actual dose rates are higher than the expected levels written on this RWP task

• Dose Alarm

• Failure of OR sweat soaked protective clothing

• If monitoring of the ED indicates that the dose alarm set point will be exceeded prior to completing the job, leave the area and contact RP. Do not wait to receive an alarm before exiting the area

• Unexpected dose rate alarm

• Unexpected wet conditions

• Work scope changes Expected Radiological Conditions General area dose rates: 0.1 mrem/hr -100 mrem/hr High contact dose rates: 0.1 mrem/hr -3000 mrem/hr Contamination levels: <1000 dpm/100cm2

-100,000 dpm/100cm2 (Beta/Gamma)

Contamination levels: 0 dpm/100cm2

-300 dpm/100cm2 (Alpha) Additional Instructions Approved on 11/12/2009 by ROBINSON, LAGRONE 0 Printed on 02/10/2010 Activated on 11/12/2009 Training Use Only Oconee Nuclear Station Radiation Work Permit Training Use Only Entry For Routine Plant And Systems Operation RWP#23 Rev: 27 Task #2 Entr for Routine Plant and S ED Alarm Set Points: Dose Alarm: 25 Dose Rate Alarm: 500 Stay Time Alarm: 55:00 High Radiation Area Entry RWP ReqUirements Dress Category/Work Description

• Dress Category "A" Work in a non-contaminated area

• Dress Category "B" Work in a non-contaminated area with contaminated material where there is NO potential for contact with

• Dress Category "C" Work in a non-contaminated area with contaminated material where there is NO potential for contact with

• Dress Category "0" Work of short duration, in open area(s) with NO obstructions that could contribute to contamination of unprotected

• Dress Category "E" Work where: (1) Complete protection of skin and clothing is NOT required; (2) Durability of surgical gloves requires

• Dress Category "F" Work in a contaminated area where complete protection of skin and clothing is NOT necessary.

• Dress Category "G" Work in a dry contaminated area.

• Dress Category "H" Work in a contaminated area.

• Dress Category "I" Hands on work with higher contaminated material or beta dose concems to hands only.

• Dress Category "N" Performing work in contaminated wet conditions.

• Modesty garments, top & bottom, are required under protective clothing where personal outer clothing is not wom Contamination Control

• Change outer rubber gloves often when handling highly contaminated material as directed by RP

• If installing a drain rig, secure hose OR tubing to floor drain

• If installing a drain rig, use hose clamps or similar device to secure hose OR tubing connections

• Install catch containments OR drain rigs to prevent spills if draining components

• Use surgical gloves in lieu of rubber gloves for the manipulation of small or specialty items as directed by RP

• Utilize facial protection (e.g. face shield, hood sock, power visor) as directed by RP

• Wear disposable (plastic) booties inside of orex booties for work in wet conditions

• Wipe down AND bag all tools and equipment prior to removal from a contaminated area as directed by RP RP Job Coverage

• Pre-job briefing required

• Start of Job, Intermittent or No Coverage for work in High Radiation Areas or less

• Timekeeping/dose cO(ltroller required for workers exposed to an actual dose rate >1500 mrem/hr OR dose will exceed 500 mrem for an individual entry Dosimetry Requirements

• 1. High noise level in the work area.

• 2. Use of head phones

• 3. Hearing impairment

• 4. Any other condition that would impair hearing an ED alarm

• An Auxiliary ED alarm is required in areas where general area dose rates are> 100 mrem/hr if any of the following conditions exist:

• Monitor ED periodically while inside the RCAfRCZ (once or twice per hour in low dose rate areas). Monitor more frequently in higher dose Approved on 11/1212009 by ROBINSON, LAGRONE 0 Printed on 02110/2010 Activated on 11/1212009 Respiratory Protection

• If weighted DAC-Hours are expected to result in greater than or equal to 4 DAC-Hours per person, perform a TEDE/ALARA evaluation

• Full Face Particulate (Additional Hood Required)

IF warranted by TEDE ALARA Evaluation OR directed by RP RP Hold Points

• Accumulated dose higher than expected

• Notify RP prior to reaching OR entry into the overhead (8 feet and above)

• Notify RP Prior to Start of Work

• RP briefing required prior to entering High Radiation Areas

• RP survey required prior to handling debris or foreign material

• RP survey required prior to handling valve/pump parts or internals Stop Work Criteria

• Actual contamination levels are higher than the expected levels written on this RWP task

• Actual dose rates are higher than the expected levels written on this RWP task

• Dose Alarm

• Failure of OR sweat soaked protective clothing

• If monitoring of the ED indicates that the dose alarm set point will be exceeded prior to completing the job, leave the area and contact RP. Do not wait to receive an alarm before exiting the area

• Unexpected dose rate alarm

• Unexpected wet conditions

• Work scope changes Expected Radiological Conditions General area dose rates: 100 mrem/hr -700 mrem/hr High contact dose rates: 0.1 mrem/hr -3000 mrem/hr Contamination levels: <1000 dpm/100cm2

-100,000 dpm/100cm2 (Beta/Gamma)

Contamination levels: 0 dpm/100cm2

-300 dpm/1 00cm2 (Alpha) Additional Instructions Approved on 11/12/2009 by ROBINSON, LAGRONE 0 Printed on 02110/2010 Activated on 11/12/2009 CANDIDATE EXAMINER REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-402 Perform Actions for Medical Emergency Admin-402 fnl Page 1 of 17 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Perform Actions for Medical Emergency Alternate Path: No Facility JPM #: Admin 402 KIA Rating(s):

System: GEN KIA: 2.4.39 Rating: 3.9/3.8 Task Standard:

Complete RP/1000I016, Enc!. 4.1 (Medical Response).

Preferred Evaluation Location:

Simulator X In-Plant __

References:

RP/1 0001016, Enc!. 4.1 (Medical Response)

Validation Time: 15 minutes Admin-402 fnl Page 2 of 17 Preferred Evaluation Method: Perform X Simulate Time Critical:

NO ======================================================================================

Candidate:

Time Start: ______ _ NAME Time Finish: __ _ Performance Rating: SAT ____ UNSAT __ _ Performance Time: ---Examiner:

________________________

__

NAME SIGNATURE DATE ======================================================================================

COMMENTS SIMULATOR OPERATOR INSTRUCTIONS:

1. Ensure ALL cables leading to MERT activation phone are disconnected.

2. Verify RP/0/S/1 000/016 clean copy available in control room RO bookshelf.

3. Ensure radios are available and operable.

Admin-402 fnl Page 3 of 17 Tools/Equipment/Procedures Needed: RP/1 0001016, Enc!. 4.1 (Medical Emergency Action -Routine Operations)

READ TO OPERATOR DIRECTION TO TRAINEE: Admin-402 fnl Page 4 of 17 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:

1. You have answered a call on 4911 (emergency line) reporting a medical emergency.

2. The caller is still on the line. INITIATING CUES: The SRO in the control room instructs you to perform the required actions for a medical emergency.

START TIME: __ _ STEP 1: Determine the appropriate procedure to use. STANDARD:

RP/O/S/1 000/016 (Medical Response) is referenced and Enclosure 4.1 (Medical Emergency Actions -Routine Operations) is determined to be the appropriate procedure to use. Enclosure 4.1 is obtained from notebook located in the front of the control room desk or from the cart in the TSC. COMMENTS:

STEP 2: Step 1.1 Complete the procedure steps that apply to this medical emergency, N/A steps not performed.

STANDARD:

Complete Enclosure 4.1 as indicated on the Key. COMMENTS:

Admin-402 fnl Page 5 of 17 SAT -UNSAT -SAT -UNSAT -

STEP 3: Step 1.2 Complete the following accident information:

• Name of person reporting injury

• Call back number

• Name of person injured

• Supervisor of injured person

• Location injury occurred

• Brief description of injury

• Date / Time Cue: The evaluator should provide a copy of the attached information sheet for the phone call data STANDARD:

The candidate obtains the above information from the evaluator by asking the appropriate questions and completes step 1.2 correctly.

Note: Refer to the completed procedure as an answer key. COMMENTS:

STEP 4: Step 1.3 IAAT MERT response is NO longer required.

THEN Exit this procedure and forward to Emergency Planning -ON03EP STANDARD:

Determine MERT is still required and continue.

COMMENTS:

Admin-402 fnl Page 6 of 17 CRITICAL STEP SAT -UNSAT -SAT -UNSAT -

STEP 5: Step 1.4 IF There is a Security Event in progress, THEN Continue with ... STANDARD:

Determine a Security Event is not in progress and N/A step 1.4. Cue: If asked, inform candidate a Security Event is not in progress.

COMMENTS:

STEP 6: Step 1.5 IF MERT activation is required THEN perform the following:

• Use Plant Page to request all MERT members to respond to the incident.

• Use the radio paging system to request MERT members to respond to the incident.

STANDARD:

Use Plant Page to request all MERT members to respond to the incident.

COMMENTS:

Admin-402 fnl Page 7 of 17 SAT -UNSAT -SAT -UNSAT -

STEP 7: Step 1.5.1 Admin-402 fnl Page 8 of 17 CRITICAL STEP Use the following directions to activate radios and pagers encoded to the MERT alert tones: SAT 1. Press the "GREEN" button labeled "MERT" on the paging console 2. Press the "RED" Button labeled "transmit" on the right bottom of the console and wait approximately 3 seconds. 3. Pick up telephone "handset" on console and press the lever located inside the handset 4. Transmit message STANDARD:

Locate paging console in the OSM booth in the simulator.

Cue: Inform candidate that the screen at the top of the phone is illuminated and contains the word "Operations" Press the "GREEN" button labeled "MERT" on the paging console Cue: Inform candidate that upper light to the left of the green MERT key illuminates green when the MERT button is depressed.

Press the "RED" Button labeled "transmit" on the right bottom of the console and wait approximately 3 seconds. Cue: Inform candidate that light above the TRANSMIT key illuminates red and a "warble tone" is heard when the TRANSMIT button is depressed.

COMMENTS:

Pick up telephone "handset" on console and press the lever located inside the handset Transmit message Gr&tded ct.£,.

kS

&s: 1) eA"06.g.,e J

-&.; +R-e

\-te 'iV&'O (/ Bu 4 1 {-ever Tro.V1Si11 dIve!

J!l-UNSAT STEP 8: Step 1.5.2 IF Paging system is inoperable in Unit 1 Control Room, THEN Request Unit 3 Control Room to activate MERT or use paging system located in TSC. STANDARD:

Determine paging system is operable and N/A the step. Cue: If ask, inform candidate that paging system is operable.

COMMENTS:

STEP 9: Step 1.5.3 Repeat Steps 1.5 and 1.5.1. STANDARD:

Repeat steps 1.5 and 1.5.1. COMMENTS:

!NOTE: Do NOT call if there is a event in Qrogress.1 STEP 10: Step 1.5.4 Call Security at one of the following extensions and request they have security MERT members respond to the emergency.

• SAS (Secondary Alarm Station) 2205 or 2767

• CAS (Central Alarm Station) 2222 or 2958 STANDARD:

Security is notified at one of the above extensions and are requested to have security MERT members respond to the emergency.

COMMENTS:

Admin-402 fnl Page 9 of 17 SAT -UNSAT -SAT -UNSAT -SAT -UNSAT -

NOTE: IF the MERT incident occurs away from the main plant (World of Energy, Keowee Hydro, Complex, etc.) THEN a shuttle bus will be required to transport responding MERT personnel.

STEP 11: Step 1.5.5 IF The incident occurs during normal working hours and shuttle bus service is required.

THEN Call extension 5353 and ... STANDARD:

Determine that this step does not apply and N/A step. COMMENTS:

STEP 12: Step 1.6 IF The incident involves a trench collapse THEN Contact Oconee Rural Fire by one of the following methods: STANDARD:

Determine that this step does not apply and N/A step 1.6 COMMENTS:

STEP 13: Step 1.7 IF A mass casualty event has occurred or is suspected, and a centralized treatment area is needed, and plant conditions allow, THEN Make a PA Announcement

... STANDARD:

Determine that this step does not apply and N/A step 1.7 COMMENTS:

Admin-402 fnl Page 10 of 17 SAT -UNSAT -SAT -UNSAT -SAT -UNSAT -

STEP 14: Step 1.8 IF Hospital evacuation is needed as determined by MERT Command or as indicated by Step 1.8.1, THEN Arrange transport of patient to the hospital by one of the following means:

• EMS (ambulance)

Dial 9-911 from the Operations Shift Manager's phone or Unit 1 Control Room SRO's phone or dial 911 from the bell South line -Unit 1, 2, and 3 Control Rooms. Refer to Step 1.8.2, prior to requesting EMS.

• Company vehicle (less serious injury)

• Personal vehicle (less serious injury) Cue: This will have to be simulated only since simulator phones do not model outside lines. STANDARD:

Determine that a Hospital evacuation is required due to the person being unconscious.

Ambulance is requested by calling 9-911. Ambulance is requested to come to Oconee Nuclear Station. STEP 15: Step 1.8.1 IF Any of the following illnesses or injuries are reported on the emergency line (4911) THEN Immediately request EMS (ambulance) to respond to the site:

• Unconsciousness STANDARD:

Determine that the injured is unconscious and perform step 1.8. (Step 14 above) Cue: This will have to be simulated only since simulator phones do not model outside lines. COMMENTS:

Admin-402 fnl Page 11 of 17 CRITICAL STEP SAT UNSAT SAT UNSAT STEP 16: Step 1.8.2 IF The patient is known or suspected to be radiologically contaminated, THEN Request from MERT ... STANDARD:

Determine that this step does not apply and N/A step 1.8.2 Cue: If asked, inform candidate that the patient is NOT contaminated.

COMMENTS:

STEP 17: Step 1.8.3 Notify Security at 2222 that the ambulance is enroute. STANDARD:

Security is notified that the ambulance is enroute COMMENTS:

STEP 18: Step 1.8.4 Notify MERT Command that the ambulance is enroute. STANDARD:

MERT Command is notified via radio that the ambulance is enroute. COMMENTS:

STEP 19: Step 1.8.5 Notify World of Energy/Public Affairs Duty Person (Ext. 4602 during operating hours). STANDARD:

World of Energy Duty Person is notified by phone. COMMENTS:

Admin-402 fnl Page 12 of 17 SAT -UNSAT -SAT -UNSAT -CRITICAL STEP SAT -UNSAT -SAT -UNSAT -

STEP 20: Step 1.9 IF Radiological contamination is involved and the person is being sent to a hospital.

THEN Complete ... STANDARD:

Determine that this step does not apply and N/A step 1.9. COMMENTS:

STEP 21: Step 1.10 Remind MERT Command that a Patient Treatment Form or Refusal of Treatment/Transport Against Medical Advice Form needs to be completed for all patients and that the completed form is to be sent to the Medical Unit for inclusion in the patient's medical file. STANDARD:

MERT Command is informed that a Patient Treatment Form needs to be completed and sent to the Medical Unit. Cue: Inform candidate to simulate only_ COMMENTS:

STEP 22: Step 1.11 IF after normal working hours ... STANDARD:

Determine that this step does not apply and N/A step 1.11. COMMENTS:

Admin-402 fnl Page 13 of 17 SAT -UNSAT -SAT -UNSAT -SAT -UNSAT -

STEP 23: Step 1.12 In the event of a fatality ... STANDARD:

Determine that this step does not apply and N/A step 1.12. COMMENTS:

STEP 24: Step 1.13 IF the employee is transferred to an offsite medical facility.

THEN notify the STA to make appropriate notifications of the transport.

STANDARD:

Notify the ST A to make appropriate notifications of the transport.

COMMENTS:

STEP 25: Step 1.14 IF A death, near death, or major traumatic injury incident occurs ... STANDARD:

Determine that this step does not apply and N/A step 1.14. COMMENTS:

STEP 26: Submit completed Enclosure 4.1, (Medical Emergency Action -Routine Operations) to the Emergency Planning Section. STANDARD:

Indicate that the completed form would be submitted to the Emergency Planning Section. Cue: Another operator will continue with this procedure and the JPM is completed.

COMMENTS:

END TASK STOP TIME: ____ _ Admin-402 fnl Page 14 of 17 SAT -UNSAT -SAT -UNSAT -SAT -UNSAT -SAT -UNSAT -

Medical Emergency Phone Call Information Sheet 1. Name person calling John Adams 2. Call back number 2322 3. Name of injured person David Smith 4. Supervisor of injured person Allan Jones 5. Location injury occurred Unit 3 HPI Pump Room Admin-402 fnl Page 15 of 17 The injured is currently located in the clean side of Unit 3's change room (3 rd floor Aux Building).

Injured is NOT contaminated

6. Description of injury The injured stood up to put on his hard hat and hit his head on a cable tray resulting in a laceration to top of head. The wound is continuing to bleed. The injured is unconscious.

7. Time Current time CRITICAL STEP EXPLANATIONS:

STEP # Explanation 3 Needed to complete the procedure.

7 Need to activate MERT. 14 Ambulance has to be requested.

Admin-402 fnl Page 16 of 17 18 MERT command should be notified so that the injured can be taken to the pickup point.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS:

Admin-402 fnl Page 17 of 17 1. You have answered a call on 4911 (emergency line) reporting a medical emergency.

2. The caller is still on the line. INITIATING CUES: The SRO in the control room instructs you perform the required actions for a medical emergency.

Enclosure

4.1 Medical

Emergency Actions Routine Operations

1. Medical Emergency Actions Routine Operations NOTE:

• Security Manager or designee in the Operational Support Center (OSC) will assume 1.1 responsibility for running this procedure Enclosure 4.2, (Medical Emergency Actions OSC/TSC Activated) after the TSC/OSC is established and turnover is accepted from Operations.

The Security Manager or designee will also assume the responsibility of MERT Communicator after activation of the TSC/OSC.

• Actions may be followed in any sequence.

• Lines left of procedure steps are used to indicate place in procedure.

Check marks are acceptable in these blanks. Complete the procedure steps that apply to this medical emergency, NI A steps not performed.

Complete the following accident information:

Name of person reporting injury 0 h n A d Q.VV'\ S Call back number

_____________

_ Name ofperson(s) injured: Supervisor of injured person: ----'--A-F-'-'-ll-'-'Q..::.../}--<---_""-'>\.....,D'-"--'-O--'--"'L:=>-.Sl---

_______ _ Location injury occurred Ul"\i=1 '3 ti P.l: -:p, \ ty\ P Ko OVVl Brief description of injury h ;.;. h e.4 A 0 C) c..1A.6\ e TIC!. 2:) ce..$v 10 To top of h%-d. WOI.ln.J.

ro bl.aeJ. 'P e.r So 1'\ 1 S U,., Co\) r"\ S C, 0 \.J S Date Tod"u S DCA+e. Time c.urre..,.+

1.3 IAAT Enclosure

4.1 Medical

Emergency Actions Routine Operations MERT response is NO longer required.

RP 10 fBI 1 00010 16 Page 2 of9 THEN Exit this procedure and forward to Emergency Planning -ON03EP {6} NOTE: Do NOT activate MERT when a security event is in progress until Security confirms that it is safe for MER T members to respond. ../ 1.5 There is a Security Event in progress, THEN Continue with Step 1.4.1 or 1.4.2 as appropriate; if NOT, go to Step 1.5. 1.4.1 The patient is outside the Protected Area, THEN Dial 9-911 from the Operations Shift Manager's phone or Unit 1 Control Room SRO's phone or dial 911 from the Bell South line: Units 112 and 3 Control Rooms. Request EMS to respond along with local law enforcement.

1.4.2 The patient is inside the Protected Area, THEN Wait until Security gives assurance that it is safe for MERT to respond before proceeding to Step 1.5 . MERT activation is required THEN perform the following:

V 1. Use Plant Page to request all MERT members to respond to the incident.

V 2. Use the radio paging system to request MER T members to respond to the incident.

1.5.1 Use the following directions to activate radios and pagers encoded to the MERT alert tones: 1. Press the "GREEN" button labeled "MERT" on the paging console 2. Press the "RED" Button labeled "transmit" on the right bottom of the console and wait approximately 3 seconds. 3. Pick up telephone "handset" on console and press the lever located inside the handset 4. Transmit message WI 11 1.5.2 /1.5.3 Enclosure

4.1 Medical

Emergency Actions Routine Operations RP/O/B/1 000/0 16 Page 3 of9 Paging system is inoperable in Unit 1 Control Room, THEN Request Unit 3 Control Room to activate MERT or use paging system located in TSC. Repeat Steps 1.5 and 1.5.1. NOTE: Do NOT call Security if there is a security event in progress.

V 1.5.4 NOTE: IF THEN c)(I/ / A-1.5.5 Call Security at one of the following extensions and request they have Security MERT members respond to the emergency.

SAS (Secondary Alarm Station) -2205 or 2767 CAS (Central Alarm Station)-2222 or 2958 the MERT incident occurs away from the main plant (World of Energy, Keowee Hydro, Complex, etc.) a shuttle bus will be required to transport responding MER T personnel.

The incident occurs during normal working hours and shuttle bus service is required.

THEN Call extension 5353 and

• Request shuttle bus to meet MER T responders at main entrance of protected area for transport to emergency scene.

• Make P A/Radio announcement that a bus has been requested to meet MER T responders at main entrance of protected area for transport to emergency scene. {3 }

0vIA 16 IF Enclosure

4.1 Medical

Emergency Actions Routine Operations The incident involves a trench collapse RP 10 fBI 10001016 Page 4 of9 THEN Contact Oconee Rural Fire by one of the following methods:

• Dial 9-911 from Ext. 3271

• Dial 9-911 from Ext. 2159

• Dia1911 from 882-7076 A. Request a response from: o Keowee Fire Department Operations Shift Manager's phone Unit 1 Control Room SRO's phone Units 1, 2, & 3 Control Room, Bell South lines o Keowee Ebenezer Fire Department o Corinth Shiloh Fire Department B. Instruct Fire Dispatcher to have fire departments enter the site through the complex entrance on Hwy. 183. All volunteers stage in complex parking lot C. Call Security at ext. 2222 and request that that they have an officer escort the fire departments to the incident location.

{7} NOTE: The primary location for Triage, should it be needed, is the Oconee Office Building.

An alternate location may need to be selected depending on the area of the plant involved in the incident.

A mass casualty event has occurred or is suspected, and a centralized treatment area is needed, and plant conditions allow, THEN Make a P A Announcement emphasizing the following:

• Location of the Triage area

• Warn that only trained medical personnel should move injured people unless there are life threatening conditions in the area.

Enclosure

4.1 Medical

Emergency Actions Routine Operations RP 10 IBII 00010 16 Page 5 of9 NOTE:

• Occupational Health Unit may call direct and request an ambulance without going V 1.8 through the emergency line (4911).

Immediate notification will then be made to the Operations Shift Manager or his designee.

• Patients with less serious injuries or illnesses may be transported to offsite medical facilities by personal or company vehicle if site Medical or MERT Command gives approval.

Hospital evaluation is needed as detennined by MERT Command or as indicated by Step 1.8.1, THEN Arrange transport of patient to the hospital by one of the following means:

• EMS (ambulance)

• Dial 9-911 from the Operations Shift Manager's phone or Unit 1 Control Room SRO's phone or dial 911 from the Bell South line -Units 112 and 3 Control Rooms. Refer to Step 1.8.2, prior to requesting EMS.

• Company vehicle (less serious injury)

• Personal vehicle (less serious injury) V 1.8.1 Any of the following illnesses or injuries are reported on emergency line (4911):

• unconsciousness

• cardiac arrest

• fall greater than 10-12 feet (qualified as multi-trauma)

• obvious fractures (with defonnity or open wounds)

• amputations

• allergic reaction WITH airway compromise (swollen lips, tongue)

• poisonous snake bite

• head injury with altered level of consciousness (confusion, disorientation)

• altered mental status (confusion, disorientation)

• seizure (grand mal)

• respiratory distress

• entrapped person

• crushing injuries THEN Immediately request EMS ( ambulance) to respond to the site.

Enclosure

4.1 Medical

Emergency Actions Routine Operations RP 10 fBI 1 00010 16 Page 6 of9 NOTE: EMS personnel will not prepare for a radiologically contaminated patient while enroute to the site unless the EMS dispatcher is requested to relay this information to them at the time of dispatch.

vJ/V'/1h.8.2 The patient is known or suspected to be radiologically contaminated, / 1.8.3 V" 1.8.4 --/ 1.8.5 THEN Request from MERT command the extent of contamination (gross contamination, PC contamination, modesty garment) and if possible contamination levels. Call Oconee Memorial Hospital, 9-882-4611 with the above information.

Notify Security at 2222 that the ambulance is enroute. Notify MERT Command that the ambulance is enroute. Notify World of EnergylPublic Affairs Duty Person (Ext. 4602 during operating hours). NOTE: IF Transportation of a radiologically contaminated person to an offsite medical facility is required.

THEN IF The NRC must be notified within eight (8) hours (ref. lOCFR50.72 (b) (3) (xii). Radiological contamination is involved and the person is being sent to a hospital.

THEN: Complete the following

1.9.1 Request

MERT Command to FAX the Patient Treatment Form to the appropriate hospital as soon as possible.

1.9.2 Determine

if a Radiation Protection Technician accompanied the contaminated patient to the hospital.

IF A RP Technician did not go with the ambulance to the hospital THEN Arrange for the first available one to go and assist the hospital with radiation monitoring and contamination control as needed

Enclosure

4.1 Medical

Emergency Actions Routine Operations RP /0 IBII 000/0 16 Page 7 of9 Notify Operations Shift Manager to refer to NSD 202 for reportability requirements.

/ 1.10 Remind MERT Command that a Patient Treatment Form or Refusal of Treatment/Transport Against Medical Advice Form needs to be completed for all patients and that the completed form is to be sent to the Medical Unit for inclusion in the patients medical file. {2} NOTE: The Environmental Health & Safety Manual has additional information for the EH&S Duty Person if needed.

IF after normal working hours; have the Operations Shift Manager or designee report the following incidents to ONS EH&S Duty Person.

• Fatality (including heart attacks at work)

• Injuries requiring offsite medical treatment

• Admission of 3 or more employees to the hospital for in-patient care

• Serious accidents (near miss) whereby personnel could have sustained a disabling injury although not resulting in an injury

• Electric contact, shock or flash bums

• Injuries or bums resulting from a fire

• Vehicle accidents

• Accident involving serious property damage

• Accident involving potential DPC liability THEN the ONS EH&S Duty Person will determine if additional people need to be notified.

J Vl.13 Enclosure

4.1 Medical

Emergency Actions Routine Operations RP /0 IBIl 000/0 16 Page 8 of9 In the event of a fatality (including all fatal heart attacks at work) or admission of 3 or more employees to the hospital for in-patient care, ensure the OSM or designee performs the following.

1.12.1 1.12.2 1.12.3 Notify EH&S Duty person who will notify OSHA (8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> oral reporting requirement).

Refer to NSD 202 for other reportability requirements.

Notify Site VP or his designee.

the employee is transferred to an offsite medical facility.

THEN notify the STA to make appropriate notifications of the transport.

NOTE: A traumatic injury refers to a physical injury. A trauma patient is someone who has suffered serious and life-threatening physical injury potentially resulting in secondary complications such as shock, respiratory failure and death. IF L THEN 1.14.1 A death, near death, or major traumatic injury incident occurs, {I} Notify Employee Assistance Program at extension 3315 or 9-704-382-7900.

Inform the EAP person of the event and the possible need to conduct a critical incident debriefing.

1.15 Submit completed Enclosure 4.1 (Medical Emergency Actions-Routine Operations) to the Emergency Planning Section. 1.16 Generate PIP with:

• time 4911 call was received

• time MER T dispatched

• location of incident. (no personal information should be included in PIP.){5} 1.17 IF Medical emergency is work related and not a personal illness THEN Contact HR duty person for completion of FFD for cause testing consideration.

• Ensure area code is entered in the call back number. HR Duty person MAY NOT be from Oconee.

Enclosure

4.1 Medical

Emergency Actions Routine Operations 1.18 Inform the employee's supervisor to notify the OSM:

• If the injury/illness is a heart attack

• If death occurs 30 days after injury/illness 1.19 If injury is a heart attack then: RP /0 IBIl 00010 16 Page 90f9 {4} 1.19.1 Document information on OSM turnover sheet and keep for 30 days. A. IAA T death occurs within 30 days of injury/illness notify EH&S duty person and NRC. 1.20 The Operations Shift Manager or designee shall ensure notification of next of kin, if applicable.

• Fatality -Appropriate Division Manager performs notifications.

• Injury requiring hospitalization

-Employee's Supervisor or Manager perform REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-405 SOD OAJ'vi ADM-405 fnl Page 1 of 14 Determine Emergency Classification and Protective Action Recommendations CANDIDATE EXAMINER Task: REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADM-405 fnl Page 2 of 14 Determine Emergency Classification and Protective Action Recommendations Alternate Path: NO Facility JPM #: Admin-405 KIA Rating(s):

System: KIA: Rating: GEN 2.4.41 2.9/4.6 Task Standard:

Appropriate classification is determined and associated Emergency Notification Form is completed.

Preferred Evaluation Location:

Simulator X

References:

RP 10lBI 1000101 RP/O/B/1000102 In-Plant _-,-X-,-_

BASIS Document (Volume "A", Section "0" of the Emergency Plan) Validation Time: 20 min. Preferred Evaluation Method: Perform Simulate _X_ Time Critical:

Yes ====================================================================================

Candidate:

Time Start: ___ _ NAME Time Finish: ----Performance Rating: SAT ___ UNSAT __ _ Performance Time: ----Examiner:

____________

___ NAME SIGNATURE DATE ====================================================================================

Comments SIMULATOR OPERATOR INSTRUCTIONS:

NONE ADM-405 fnl Page 3 of 14 ADM-405 fnl Page 4 of 14 Tools/Equipment/Procedures Needed: RP/O/B/1000101 1 RP/O/B/1000102 BASIS Document (Volume "A", Section "0" 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:

Unit 2 at 100% power 0900: Reactor trip due a Sheared RCP shaft on 2A 1 RCP 0900: Control Room has indications that the 2A 1 RCP Seals have failed 0904: ES 1 & 2 actuated

• RCS pressure = 1580 psig and decreasing

• RB pressure = 4.7 psig and increasing

• The 2A HPI pump fails to Auto start and cannot be started manually 0910: RCS Saturated and stable at 1000 psig. All RCPs have been secured

• RB pressure peaks at 9.7 psig 0912: 2RIA-57 reads 350 R/HR stable 0915: RB Pressure = 0.2 psig and stable INITIATING CUE: You are to perform the required actions of the Emergency Coordinator by referring to RP/O/B/1 000/01, Emergency Classification:

1. Determine Emergency Classification and record the time here. _____ _ 2. Complete appropriate Emergency Notification Form for the current conditions.

THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinator's judgment while classifying the event. When required, Jim Turner will maintain the Emergency Coordinator's Log, assume the duties of the Control Room Offsite Communicator and activate the ERO pagers if desired.

STARTTIME:

__ _ STEP 1: Classify the Event at 0915 , STANDARD:

Refer to RP/O/B/1000101 (Emergency Classification)

Enclosure 4.1 (Fission Product Barrier Matrix). Classify the event as a "General Emergency" due to the following:

Fission Product Barrier Matrix

• 5 points for RCS Barriers due to 1 RIA-57 reading

• 5 points for Fuel Clad Barriers due to 1 RIA-57 reading

• 3 points for Containment Barriers due to (Rapid unexplained containment pressure decrease after increase" 13 points total results in a General Emergency

• *Determine 4.1.G.2 Loss of all 3 Barriers Time for Classification

• Note: Required to classify the event within 15 minutes of starting.

GO TO RP/O/B/10001002 (Control Room Emergency Coordinator Procedure)

COMMENTS:

STEP 2: Step 1.1 Events have occurred ... STANDARD:

Determine Emergency Plan has been activated and sign step. COMMENTS:

STEP 3: Step 2.1 IF No EAL exists ... STANDARD:

Determine a General Emergency does exist and N/A the step. COMMENTS:

ADM-405 fnl Page 5 of 14 CRITICAL STEP SAT -UNSAT -SAT -UNSAT -SAT -UNSAT -

STEP 4: Step 2.2 Declare the appropriate Emergency Classification level. Classification (UE, Alert, SAE, GE) Time Declared:

STANDARD:

Declare a General Emergency due to: Fission Product Barrier Matrix Determine Time of Declaration of General Emergency is time declared in Step 1. COMMENTS:

STEP 5: Step 2.3 IF a Security event is in progress STANDARD:

Determine a security event is NOT in progress and N/A step. COMMENTS:

STEP 6: Step 2.4 IF assistance from ERO personnel is desired/required:

THEN activate ERO pagers from the ERO Pager Activation Panel:

• For an EMERGENCY press "Test" button then press button 1

• For a DRILL press "Test" button then press button 3 STANDARD:

Determine that assistance is desired. Note: The Control Room Offsite Communicator will activate the ERO pagers. COMMENTS:

---

ADM-405 fnl Page 6 of 14 SAT UNSAT SAT UNSAT SAT UNSAT STEP 7: Step 2.5 Appoint Control Room Offsite Communicator(s) and perform the following:

• Record Name

• Notify Offsite Communicator to REFER TO RP/O/B/10001015A, Immediate Actions steps 2.1 and 2.2 AND Enclosure 4.7 (Guidelines for Manually Transmitting a Message) in preparation for notifying offsite agencies.

STANDARD:

A Control Room Offsite Communicator is appointed and name is recorded.

COMMENTS:

STEP 8: Step 2.6 IAAT Changing plant conditions require an emergency classification upgrade, THEN Notify Offsite Communicator to complete the in-progress notifications per RP/O/B/1 OOO/15A, (Off site Communications From The CR) AND Re-initiate a clean copy of this procedure for the upgraded classification and stop this procedure.

STANDARD:

Determine that an upgrade is NOT required.

COMMENTS:

---

ADM-405 fnl Page 7 of 14 SAT UNSAT SAT UNSAT STEP 9: Step 2.7.1 Obtain the applicable Offsite Notification form in the control room and complete as follows:

• Ensure EAL # as determined by RP/0/B/1000/001 matches Line 4 . STANDARD:

EAL # 4.1.G.2 is selected.

COMMENTS:

STEP 10: Step 2.7.2 Line 1 -Mark appropriate box "Drill" or "Actual Event" STANDARD:

Mark "Drill" COMMENTS:

STEP 11: Step 2.7.3 Line 1 -Enter Message # STANDARD:

Enter Message # 1 COMMENTS:

ADM-405 fnl Page 8 of 14 CRITICAL STEP SAT -UNSAT -SAT -UNSAT -CRITICAL STEP SAT -UNSAT -

STEP 12: Step 2.7.4 Line 2 -Mark Initial STANDARD:

Mark Initial COMMENTS:

STEP 13: Step 2.7.5 Line 6 -A. Mark "Is Occurring" if any of the following are true: * . RIAs 40, 45, or 46 are increasing or in alarm

• If containment is breached * . Containment pressure>

1 psig Mark "None" if none of the above is applicable.

STANDARD: "Is Occurring" is pre-marked on form. COMMENTS:

STEP 14: Step 2.7.6 Line 7 -If Line 6 Box B or C is marked, mark Box D. Otherwise mark Box A STANDARD: "Under Evaluation" is pre-marked on form. COMMENTS:

ADM-405 fnl Page 9 of 14 CRITICAL STEP SAT -UNSAT -SAT -UNSAT -SAT -UNSAT -

STEP 15: Step 2.7.7 Line 8 -Mark "Stable" unless an upgrade or additional PARs are anticipated within an hour. * . Refer to Enclosure 4.9, (Event Prognosis Definitions)

STANDARD:

Mark "Stable".

COMMENTS:

STEP 16: Step 2.7.8 Line 10 -Military time and date of declaration (Refer to date/time in Step 2.2) STANDARD:

Enter date and time entered in Step 2.2. COMMENTS:

STEP 17: Step 2.7.9 Line 11 -If more than one unit affected, mark "All" STANDARD:

Mark Unit 2. COMMENTS:

ADM-405 fnl Page 10 of 14 CRITICAL STEP SAT -UNSAT -CRITICAL STEP SAT -UNSAT -SAT -UNSAT -

STEP 18: Step 2.7.10 Line 12 -Mark unit(s) affected (reference Line 11) AND enter percent power for each unit affected.

• If affected unit is shutdown, then enter shutdown time and date. STANDARD:

For Unit 2 Enter 0900 and today's date. Note: Other Unit's data is NOT required for the initial notification.

COMMENTS:

STEP 19: Step 2.7.11 Line 13 -If the OSM has no remarks, write "None" STANDARD:

Enter None. COMMENTS:

STEP 20: Step 2.7.12 If Condition "A" exists ensure following PAR's are included on Line 5.

• Evacuate:

Move residents living downstream of the Keowee Hydro Project dams to higher ground

• Other: Prohibit traffic flow across bridges identified on your inundation maps until the danger has passed. STANDARD:

Determine Condition "A" does NOT exists and N/A step. COMMENTS:

ADM-405 fnl Page 11 of 14 SAT -UNSAT -SAT -UNSAT -SAT -UNSAT -

STEP 21: Step 2.7.13 Line 17 -OSM signature, CURRENT Time/Date STANDARD:

Signs form and enters CURRENT Time/Date.

Form complete within 15 minutes of classification in step 2.2. COMMENTS:

END TASK TIME STOP: __ _ ADM-405 fnl Page 12 of 14 CRITICAL STEP SAT UNSAT CRITICAL STEP EXPLANATIONS:

STEP # Explanation 1 Required to classify event as a General Emergency.

9 Ensures that the correct communication form is selected.

11 Required to accurately complete notification form. 12 Required to accurately complete notification form. 15 Required to accurately complete notification form. 16 Required to accurately complete notification form. ADM-405 fnl Page 13 of 14 21 Required to complete communication form with 15 minutes of classification.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) 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:

Unit 2 at 100% power 0900: Reactor trip due a Sheared RCP shaft on 2A 1 RCP 0900: Control Room has indications that the 2A 1 RCP Seals have failed 0904: ES 1 & 2 actuated

• RCS pressure = 1580 psig and decreasing

• RB pressure = 4.7 psig and increasing

• The 2A HPI pump fails to Auto start and cannot be started manually 0910: RCS Saturated and stable at 1000 psig. All RCPs have been secured

• RB pressure peaks at 9.7 psig 0912: 2RIA-57 reads 350 R/HR stable 0915: RB Pressure = 0.2 psig and stable INITIATING CUE: You are to perform the required actions of the Emergency Coordinator by referring to RP/O/B/1 000/01, Emergency Classification:

1. Determine Emergency Classification and record the time here. _____ _ 2. Complete appropriate Emergency Notification Form for the current conditions.

THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinator's judgment while classifying the event. When required, Jim Turner will maintain the Emergency Coordinator's Log, assume the duties of the Control Room Offsite Communicator and activate the ERO pagers if desired.