ML101520250
| 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
Admin-1 14 fnl Admin-114 Page 11 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE ADMIN-1 14 ADMIN-114 MODE CHANGE VERIFICATION FOR MODE 1&2 ENTRY RO ~.rf?J)
CANDIDATE EXAMINER
Admin-114 Admin-1 14 fnl fnl Page Page 22 of of 99 REGION IIII REGION INITIAL LICENSE INITIAL LICENSE EXAMINATION EXAMINATION JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE Task:
Mode Change Verification Alternate Path:
No Facility JPM #:
Admin-114 KIA Rating(s):
System: Generic K/A:
KIA: 2.1.25 Rating: 3.9/4.2 Task Standard:
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_X In-Plant _ _ Perform X X Simulate
References:
PT/1/A!06001001 B, Enclosure 13.23 PT/1/A/06001001 13.23 Validation Time: 20 minutes Time Critical: NO
========================================================================
Candidate: Time Start: - - - -
NAME Time Finish: _ __
Performance Rating: SAT ___ UNSAT _ __ Performance Time: - - - -
Examiner: _ _ _ _ _ _ _ _ _ _ _ __ ---------- _____ ~/--_-
NAME SIGNATURE SIGNATURE DATE
========================================================================
COMMENTS COMMENTS
Admin-1 14 fnl Admin-114 Page 3 of 9 SIMULATOR OPERATOR INSTRUCTIONS:
Snap2l3
- 1. Recall Snap 213 ADM IN-i 14
- 2. Import files for ADMIN-114
- 3. Update CBAST Boron 10620 ppmB
- 4. Place Dummy Bistable Prop in B RPS Channel (RCP/flux trip)
G0t0RUN
- 5. Go to RUN
Admin-1 14 fnl Admin-114 fnl Page 4 of 9 Page4of9 Tools/EguipmentlProcedures Needed:
Tools/Equipment/Procedures Needed:
PT!11A106001001 B PT/1/A/06001001 B (Instrument Surveillance Prior Prior To Mode Mode Change) Enclosure Enclosure 13.23, 13.23, Entering Modes Entering Modes 11 & 2 From From Mode Mode 33 READ TO OPERATOR DIRECTION TO TRAINEE:
II 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. II 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 II provided you.
INITIAL CONDITIONS:
Unit 11 startup in progress Unit 11 in MODE 3 PTI1IAIO600IOO1 B (Instrument Surveillance Prior To Mode Change) Enclosure 13.23, PT/1/A/0600/001 (Entering Modes 1 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 PT/11A106001001 B (Instrument Surveillance Prior To Mode Change) Enclosure 13.23, Entering Modes 1 I & 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.
Admin-114 Admin-1 14 fnl Page 55of9 of 9 START TIME: _ __
1:
STEP 1: RPS Instrumentation RC Temperature TH (A RPS (A Loop)
Loop) CRITICAL STEP Verify computer readouts agree within 3°F (If OAC unavailable, 5°F in
STANDARD: Determine computer points DO NOT agree within 3°F by calling points up on the OAC. - UNSAT U N SAT 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 (B Loop)
Verify computer readouts agree within 3°F (If OAC unavailable, 5°F in
STANDARD: Determine computer points DO agree within 3°F by calling pOints points up on the OAC. - UNSAT CUE: If candidate goes to RPS cabinet, inform them that the RPS cabinet agrees with the OAC computer pOintspoints COMMENTS:
STEP 3: RPS Instrumentation RC Flow Verify total flow agrees within 4800 klbm/hr
- SAT AND Verify NO computer alarms for high flow present.
UNSAT 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 Admin-1 14 fnl Page Page 6 of of 9 STEP 4:
STEP CBAST CBAST CRITICAL CRITICAL STEP STEP 1100 ft3 of 11,000 Verify equivalency of 1100 11,000 ppm ppm boron per OP/O/Al11 boron per 08/001 OP/OIA/l 108/001 And General SAT (Curves And General Information).
Information). -
STAN DARD:
STANDARD: Obtain CBAST level and boron concentration from the OAC or from Boron Board and CBAST level gauge. (66 inches and 10620 10620 ppmB) - UNSAT Determine CBAST is in the inoperable range of Enclosure 4.15 (CBAST Concentration Vs. Level Curve)
COMMENTS:
- CRITICAL STEP
- SAT Verify no trips present.
Verify status annunciators operable (lamp test).
- UNSAT STANDARD: *Determines that Dummy Bistable is installed on 'B'
- Determines B RPS channel (RCP/flux trip).
Verify no trips present by observing Statalarms on 1iSA-i.
SA-i.
- Determines that 1
- Determines 1SA-5/E-2 SA-5/E-2 (RP Channel B 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 ISA-51E-2 then inform them that we have replaced the light bulbs in 1ISA-51E-2 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.
- SAT STANDARD: Determine 4 RCPs RCP5 are in operation by observing red on lights lit and normal pump amps. Determine RCS flow is indicated on RC Flow gauge 1UB1.
on 1UB1.
- UNSAT UN SAT COMMENTS:
COMMENTS:
Admin-114 Admin-1 14 fnl fnl Page 7 of 9 Page7of9 STEP 7:
STEP 7: Inform CR Inform CR SRO SRO ofof any any surveillances surveillances that that are are NOT NOT met.
met. CRITICAL CRITICAL STEP STEP STANDARD:
STANDARD: Candidate should Candidate should determine determine that that the the following following surveillances surveillances are are not not met.
met. SAT SAT
- SR 3.3.1.1 for SR 3.3.1.1 for RPS Instrumentation RC RPS Instrumentation RC Temperature Temperature THTH (A (A Loop)
Loop) is is not met.
not met.
- SR 16.5.13.1 for SR 16.5.13.1 for the the CBAST CBAST is is not not met.
met. UNSAT UNSAT
- SR 3.3.1.1 SR 3.3.1.1 Dummy Dummy Bistable Bistable is is installed installed Cue: Ask Cue: Ask candidate about any surveillances that that were were not met if not addressed.
COMMENTS:
COMMENTS:
END TASK STOP TIME: _ _ _ __
Admin-1 14 fnl Admin-114 Page Page 8 of 9 CRITICAL STEP EXPLANATIONS:
STEP # Explanation 11 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.
CANDIDATE CUE CANDIDATE CUE SHEET (TO BE (TO BE RETURNED RETURNED TO EXAMINER EXAMINER UPON UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
INITIAL CONDITIONS:
Unit 11 startup in in progress Unit 11 in MODE 3 PT/1/A10600!OO1 B (Instrument Surveillance Prior To Mode Change) Enclosure 13.23, PT/1/A/06001001 (Entering Modes 11 & 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 PTI1IAIO600/OO1 B (Instrument Surveillance Prior To Mode Change) Enclosure 13.23, Entering Modes 11 & 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/lIAIo600/ool PT/I/A/0600/001 B Instrument Surveillance Prior To Mode Change Revision No.
032 Electronic Reference No.
0P00964Z OPOO964Z Continuous Use PERFORMANCE II
- * * * * * * *
- UNCONTROLLED FOR PRINT * * * * * * *****
(ISSUED) - PDF Format
PT/l1 A/0600/001 BB PT/1/A/0600/001 Page 22 of of55 Instrument Surveillance Prior To Mode Change
- 1. Purpose 1.1 verifY proper operation of various instruments and systems prior to Mode change.
To verify
- 2. References 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)
- 3. Time Required 3.1 30 minutes
- 4. Prerequisite Tests None
- 5. Test Equipment None
- 6. Limits And Precautions 6.1 PT/O/ A/0600/o0 11 A (Loss Of Computer) should be referred to upon a loss of computer PT/0/A/0600/00 or loss of a computer point or function needed for a surveillance.
PT/1/A/0600 PT/l1 A/06001001/00 1 BB Page 33 of Page 5 of5 6.2 6.2 When using When using Computer Computer Points Points to perform aa surveillance, to perform the Computer surveillance, the MUST be Points MUST Computer Points be used from used from aa Computer Computer Display Screen, which Display Screen, also indicates which also the Quality indicates the of the Computer Quality of the Computer Point.
Point.
- Computer Computer Point Point Quality Quality and MUST indicate Value MUST and Value indicate as as follows to be follows to be used for aa used for surveillance:
surveillance:
- GOOD with aa Value GOOD with represents actual that represents Value that plant conditions actual plant conditions
- INHB with INHB plant conditions actual plant with aa Value that represents actual
- LALM with LALM with aa Value that represents actual Value that plant conditions actual plant conditions
- HALM with aa Value that HALM plant conditions that represents actual plant
- 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 10.1 Data requirements specified specified in applicable Enclosures.
11.
- 11. Acceptance Criteria 11.1 11.1 Systems Systems or or components components meet meet TS TS or SLC requirements or SLC applicable to requirements applicable step.
surveillance step.
to surveillance
PT/llAI06001001 B PT/1/A/0600!OOl Page4of5 Page 4 of5
- 12. Procedure 12.1 Perform component checks prior to changing Modes within the required time frames Perfonn 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 Dixson Meter Infonnation" Dixsons listed on Enclosure "Dixson T are on an enhanced Information surveillance interval.
12.3.2 Dixson Meter Infonnation" IF any Dixson listed on Enclosure "Dixson Information are found to be blinking with a reading of zero, no action is required unless a failure is suspected.
12.3.3 Dixson Meter Infonnation" Dixsons NOT listed on Enclosure "Dixson Information 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 11 13.2 Entering Mode 33 From Modes 11 & &2 13.3 RCS 325°F Surveillances Prior To ReS::;
13.4 Entering Mode 4 From Mode 33 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
PT;l/
PT/1/A/0600/00l A/06001001 B Page 5 of5 of 5 13.9 Entering Mode 6 From No Mode 13.10 Surveillances Prior To FTC Level < 21.34 ft Above Top OfRxV Of RxV Flange 13.11 Surveillances Prior To RxV Head Installed 13.12 Entering Mode 55 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 ModeS5 13.16 Surveillances Prior To SGs Required For Heat Removal 13.17 Entering Mode 33 From Mode 4 13.18 Surveillances Prior To RCS >
13.l8 >325°F 325°F 13.19 Surveillances Prior To RCS > 350°F
>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 11 && 2 From Mode 3 3 13.24 Surveillances Prior To >> 20% RTP 13.25 Surveillances Prior To >> 40% RTP 13.26 Dixson Meter Information Appendix
Enclosure 13.23 Enclosure 13.23 PT 11;AI0600/o0 1 B PT/1/A/0600/OO1 B Entering Mode 11 && 2 From Mode 3 Page 11 of3 of 3
- 1. Initial Conditions
~ 1.1 c.ft) 1.1 Unit is in Mode 3.
~1.2 cf.J 1.2 Review Limits And Precautions.
A(OTE: SRs are only valid for:::;
for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> once enclosure is started. When> 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from start time, a new enclosure is required.
~1.3 Date and Time Enclosure started Tvd.a. '::> I/ 00 7 L) 0
- 2. Procedure 2.1 Perform instrument checks as specified.
Enclosure 13.23 11;A/0600100 1 B PT/1/A/0600/O01 PT Entering Mode 11 & 2 From Mode 3 Page 2 of3 of 3 COMPONENT INITIALS COMPUTER REQUIRED CONDITIONS SR 3.3.1.1 RPS Instrumentation 01A1692 Verify computer readouts agree within 3°P 3°F (If T H (A Loop)
RC Temperature TH(A OlA1693 01A1693 OAC unavailable, 5°F 5°P in RPS Cab).
IF any of CR RCS temperature selectors are jj changed, notify Rx Engineering to evaluate and update Enclosure "Loop ~T Vs.
Loop AT Vs. Reactor Power Power" ofPTIlIA/06001001 of PT/1/A!0600100 1 (Periodic Instrument Surveillance) for new selected inputs.
SR 3.3.1.1 RPS Instrumentation 01A1694 Verify computer readouts agree within 3°F 3°P (If TH (B Loop)
RC Temperature TH(B 01A1695 01A1695 OAC unavailable, 5°F 5°P in RPS Cab).
IF any of CR RCS temperature selectors are changed, notify Rx Engineering to evaluate and update Enclosure Loop ~T Vs.
"Loop AT V s. Reactor Power Power" PTI1IA/0600100 1 (Periodic Instrument of PT/1/A10600/001 Surveillance) for new selected inputs.
Surveillance)
SR 3.3.1.1 RPS Instrumentation 01A1549 Verify total flow agrees within 4800 klbm!hr klbmlhr RC Flow RC Plow 01A0877 01A0877 AND 01A1420 01A1420 Verify NO computer alarms for high flow OlA17l2 01A1712 present.
present.
SR 3.1.6.1 SR 3.1.6.1 APSR Alignment Limits REG GDREG GD Verify position of Verify of each APSR APSR within 6.5%
6.5% of of c.p0 1D.LJ group average.
SR 3.2.1.1 SR 3.2.1.1 Position Limits Regulating Rod Position REG GDREG GD Verify regulating rod groups within sequence Verify sequence C?0 di and overlap limits in COLR.
SR 3.2.1.2 3.2.1.2 Position Limits c.,~W REG GDREG Verify regulating rod groups within position position SR Regulating Rod Position ,.. GD Verify curve in limits on curve in COLR.
COLR.
Enclosure 13.23 PT /1;A/0600/o0 1 B PT/1/A/0600/OO1 Entering Mode 1 && 2 From Mode 3 Page 3 of3 of 3 COMPONENT fNITIALS INITIALS COMPUTER REQUIRED CONDITIONS SR 3.1.4.1 Control Rod Group Alignment GD REG GDREG Verify all Control Rods in each Group agree Limits GD SAFETY within +/- 3.5% of group average.
C(/w oc2 IF a Control Rod is >> +/- 3.5% of its Group average, refer to OP/1IA11105/019 OP/i/All 105/0 19 (Control Rod Drive System).
Drive_System).
SR 3.1.5.1 Safety Rod Position Limits CPW GD SAFETY PT Panel PI Verify each safety rod fully withdrawn.
SR 16.5.13.1 CBAST 01E0161 Verify equivalency of 1100 ft3 3 of 11,000 ppm ft OP/0/A/1 108/001 (Curves And boron per OP/o/AlI10S/001 General Information).
SR 3.3.1.1 RPS Instrumentation Verify no Dummy Bistable installed.
RP RCP/Flux Trip Verify no trips present.
Verify status annunciators operable (lamp test).
Verify_status_annunciators_operable_(lamp_test).
SR 3.1.7.1 Position Indicator Channels Verify all Relative Rod Position indications P1 Panel PI cpJ agree within 5% of Absolute Rod Position indications.
IF NOT, notify Duty Rx Engineer for evaluation of core parameters and recommended actions.
SR 3.4.4.1 SR3.4.4.1 RCS Loops Verify required RCPs (3 or 4) in operation with RCS flow indicated.
RCS_flow_indicated.
Duke Energy Procedure No.
Oconee Nuclear Station PT/l/A106001001 PT/I/A/0600/001 B B Instrument Surveillance Prior To Mode Change Revision No.
032 Electronic Reference No.
Electronic 0P00964Z OP00964Z Continuous Use PERFORMANCE I
- * * * * * * * *
- UNCONTROLLED FOR PRINT * * * * * * * * * *
- * * * * * * * * *JIJCQNTROLLEDFQRpRJNT* * * * * * * * * *
~UED) - PDF Format IUED) -
/
PT/1/A/0600/O01 PT/ll AI06001001 B Page 2 of5 of 5 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 2.1 Technical Specifications (TS) 2.2 DPC/Oconee DPCIOconee Nuclear Station Core Operating Limits Report (COLR) 2.3 UFSAR Chapter 16 Selected Licensee Commitments (SLC)
- 3. Time Required 3.1 30 minutes
- 4. Prerequisite Tests None
- 5. Test Equipment None
- 6. Limits And Precautions 6.1 PT/OIAI0600100 11 A (Loss Of Computer) should be referred to upon a loss of computer PTIOIA/0600/00 or loss of a computer point or function needed for a surveillance.
PT/1/A/0600/0Ol PTf1/ B Af0600fOOl B Page 33 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;l/
PT/1/A/0600/OO1 Al0600/001 B of 5 Page 4 of5
- 12. Procedure 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 Dixsons listed on Enclosure "Dixson Dixson Meter Information" Information are on an enhanced surveillance interval.
12.3.2 Dixson Meter Information" IF any Dixson listed on Enclosure "Dixson Information are found to be blinking with a reading of zero, no action is required unless a failure is suspected.
12.3.3 Dixsons NOT listed on Enclosure "Dixson Dixson Meter Information" Information are on a surveillance interval. These Dixsons have alternate methods of verifying input signal is valid.
- 13. Enclosures 13.1 l3.1 Entering Mode 2 From Mode 11 13.2 l3.2 Entering Mode 33 From Modes 11 & &2 13.3 RCS Surveillances Prior To ReS ~ 325°F 13.4 l3.4 Entering Mode 4 From Mode 33 13.5 l3.5 Entering Mode 55 From Mode 4 13.6 l3.6 Entering Mode 6 From Mode 55 13.7 l3.7 Surveillances Prior To Fuel Movement In RB 13.8 l3.8 Entering No Mode From Mode 6
PT/1/A10600/001 PTf1/ Al0600fOOI B Page5of5 Page 5 of5 13.9 Entering Mode 6 From No Mode 13.10 Surveillances Prior To FTC Level <<21.34 Of RxV Flange 21.34 ft Above Top OfRxV 13.11 Surveillances Prior To RxV Head Installed 13.12 Entering Mode 55 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 55 13.16 Surveillances Prior To SGs SOs Required For Heat Removal 13.17 Entering Mode 33 From Mode 4 13.18 Surveillances Prior To RCS >>325°F 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 11 &
& 2 From Mode 33 To > 20% RTP 13.24 Surveillances Prior To>
13.25 Surveillances Prior To > 40% RTP 13.26 Dixson Meter Information Appendix
Enclosure 13.23
/1;A/0600/00 1 B PT/1/A/0600/OO1 PT Entering Mode 1 & & 2 From Mode 3 Page 11 of3 of 3
- 1. Initial Conditions
>< 1,1 1.1 Unit is in Mode 3.
X X 1.2 Review Limits And Precautions.
NOTE: for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> once enclosure is started. When> 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from start time, a new enclosure is required.
SRs are only valid for:::;
41.31.3 Date and Time Enclosure started Tad Ct~ / D 0?7 00 D D
- 2. Procedure 2.1 Perform instrument checks as specified.
Enclosure 13.23 PT/1/A/0600/0O1 B PT/I/A/06001001 Entering Mode 11 & 2 From Mode 3 Page 2 of3 of 3 COMPONENT INITIALS COMPUTER REQUIRED CONDITIONS SR 3.3.1.1 RPS Instrumentation 01A1692 OlA1692 Verify computer readouts agree within 33°Fof (If RC Temperature TH (A Loop) O1A1693 OlA1693 OAC unavailable, 5°F in RPS Cab).
IF any of CR RCS temperature selectors are changed, notify Rx Engineering to evaluate and Loop .6.
update Enclosure "Loop AT TV s. Reactor Power" Vs. Power ofPTIl/AI06001001 of PT/i /A/0600/00 1 (Periodic Instrument Surveillance) for new selected inputs.
SR 3.3.1.1 RPS Instrumentation 01A1694 Verify computer readouts agree within 33°Fof (If RC Temperature TTHH(B Loop) s ~(le.d S 01A1695 OAC unavailable, 5°F in RPS Cab).
0 F of=F IF any of CR RCS temperature selectors are changed, notify Rx Engineering to evaluate and Loop .6.
update Enclosure "Loop AT Vs.
TV s. Reactor Power" Power ofPTIlIAl06001001 of PT/1/A10600/0O 1 (Periodic Instrument Surveillance) for new selected inputs.
SR 3.3.1.1 RPS Instrumentation ISf1~
S ;yJ 01A1549 Verify total flow agrees within 4800 klbrnlhr klbmlhr RC Flow D ff-ff.. 01A0877 01A1420 AND Verify NO computer alarms for high flow 01A1712 present.
SR 3.1.6.1 APSR Alignment Limits ex GD REG GDREG Verify position of each APSR within 6.5% of group_average.
group average.
SR 3.2.1.1 Regulating Rod Position Limits b< GD REG GDREG Verify regulating rod groups within sequence and_overlap_limits_in_COLR.
and overlap limits in COLR.
b<~
SR 3.2.1.2 Regulating Rod Position Limits GD REG GDREG Verify regulating rod groups within position
- limits on curve in COLR.
Enclosure 13.23 PT/1/A/0600/O0l B PTil/A/0600100l B Entering Mode 11 & 2 From Mode 3 Page 3 of3 of 3 COMPONENT INITIALS COMPUTER REQUIRED CONDITIONS SR 3.1.4.l 3.1.4.1 Control Rod Group Alignment GD REG GDREG Verify all Control Rods in each Group agree Limits GD SAFETY within +/- 3.5% of group average.
IF a Control Rod is > +/- 3.5% of its Group is>
average, refer to OPIlIAI1l05/0l9 OP/i/A/i 105/019 (Control Rod Drive System).
SR 3.1.5.1 SR l6.5.13.l 16.5.13.1 Safety Rod Position Limits CBAST
>< GD SAFETY PT_Panel PI Panel 01E0161 OlE016l Verify each safety rod fully withdrawn.
3 of 11,000 ppm ft Verify equivalency of 1100 f1"'
boron per OP/O/AI11081001 OP/0/A/l 108/00 1 (Curves And General Information).
SR 3.3.1.1 RPS Instrumentation Verify no Dummy Bistable installed.
RP RCP/Flux Trip Verify no trips present.
Verify status annunciators operable (lamp test).
SR 3.1.7.1 Position Indicator Channels Verify all Relative Rod Position indications PT Panel PI agree within 5% of Absolute Rod Position indications.
IF NOT, notify Duty Rx Engineer for evaluation of core parameters and recommended actions.
SR 3.4.4.1 RCS Loops Sii.sI'7~J S SJ Verify required RCPs (3 or 4) in operation with off RCS flow indicated.
Admin Admin 113 113 fnl fnl Page Page 11 of of 88 REGION IIN REGION INITIAL LICENSE EXAMINATION EXAMINATION PERFORMANCE MEASURE JOB PERFORMANCE Admin 113 ROOAJL,/
CALCU LATE AN ESTIMATED CRITICAL ROD CALCULATE POSITION CANDIDATE EXAMINER
Admin 113 Admin 113 fnl fnl Page Page 22 of of 88 REGION IIII REGION INITIAL LICENSE INITIAL LICENSE EXAMINATION EXAMINATION JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE Task:
Calculate an Calculate Estimated Critical an Estimated Critical Rod Rod Position Position Alternate Path:
Path:
No No Facility JPM #:
CRO-037 CRO-037 K/A Rating(s):
KIA System: GEN K/A:
KIA: 2.1.19 Rating: 3.9/3.8 Task Standard:
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/i/A/i PT/1 IA/11103/15 Encl. 13.4 (Computerized ECP Calculation) 03/15 (Reactivity Balance Procedure), End.
Validation Time: 17 17 minutes Time Critical: NO
========================================================================
Candidate: Time Start: _ _ __
NAME Time Finish: - - - -
Performance Rating: SAT ___ UN SAT _ __
UNSAT Performance Time: - - - -
Examiner: _ _ _ _ _ _ _ _ _ _ _ __ - - - - - - - - - -______/1_ _- -
NAME SIGNATURE SIGNATURE DATE
========================================================================
COMM COMMENTSENTS
Admin 113 113 fnl Page 3 of 8 SIMULATOR OPERATOR INSTRUCTIONS:
None
Admin Admin 113 113 fnl fnl Page Page 44 of of 88 Tools/Equipment/Procedures Needed:
Tools/Equipment/Procedures Needed:
PT/i /A/1103/15 (Reactivity PT/1/A/1103/15 (Reactivity Balance Balance Procedure),
Procedure), Enc!.
End. 13.4 13.4 (Computerized (Computerized ECPECP Calculation)
Calculation)
READ TO OPERATOR READ DIRECTION TO TRAINEE:
DIRECTION TRAINEE:
II 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. II 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 II provided you.
INITIAL CONDITIONS:
Unit 11 operated from 1/15 1/154/3
- 4/3 at 100% power 1000 4/3 1000 - Forced reactor shutdown is commenced at 10%/hr EFPD = 127
=
Unit is NOT returning from a "Forced Forced Outage" Outage PRESENT CONDITIONS:
4/10 14001400 Unit #1 Startup in progress RCS Boron = = 1325 RCS Temperature =532°F.
Group 88 positioned at 35% withdrawn INITIATING CUES:
The Control Room SRO The SRO directs directs youyou to to calculate an an original estimated estimated critical rod position position for 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> hours from the present time per PT/1/A/1103/15, the present time per PT/1 IA/11 03/15, Reactivity Reactivity Balance Balance Procedure.
Procedure.
Print out out the calculation once itit is is completed.
Admin 113 113 fnl Page 5 of 8 START TIME: _ __
STEP1:
STEP 1: Step2.1 Step 2.1 This enclosure must must be performed twice - the second is the separate
- SAT verification. Circle whether this is the original or the verification.
STANDARD: Candidate should circle "original" original and N/A the bullet step. UNSAT Continue to Step 2.2 COMMENTS:
I CAUTION: IF the power history information from the last equilibrium Xe/Sm condition is SAT NOT input into the code, significant error may result. I -
STEP 2: Step 2.2 Obtain the power history back to the last time of Xenon equilibrium to - UNSAT perform the Xenon calculation from a source such as PI Pt 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.
wilt attach the power history to this Candidate indicates that he will enclosure.
Cue: Consider the Candidate Cue sheet your power history and that it is attached as directed Continue to Step 2.3 COMMENTS:
Admin Admin 113 113 fnl fnl PaQe Page 66 of of 88 STEP 3:
STEP 3: Step 2.3 Step 2.3 Open RhoCalc.
Open RhoCalc.
- SAT SAT STANDARD:
STANDARD: Candidate locates Candidate locates the the RhoCalc RhoCalc icon icon on on the the PC PC and and opens opens the the program.
program.
Note: For Note: For the the purposes purposes of this JPM of this JPM the RhoCalc program the RhoCalc program will will already already be be open open on on
- UNSAT UNSAT the computer.
the computer.
Continue to Continue Step 2.5 to Step 2.5 COMMENTS:
COMMENTS:
STEP 4:
STEP Step 2.4 Step 2.4 *CRITICAL STEP
- CRITICAL STEP INPUT appropriate data for the estimated critical rod position calculation, Calculate ECP",
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
- RCS -
- *Current Boron Concentration
- Current Concentration - 1325 ppm
- *EFPD - 127
- EFPD -
- *Group 8 position - 35% withdrawn
- Group
- *Power History:
- *Power 4/3 @1 000 - 100%
@1000 -
4/3 @2000-
@2000 0%
4/10 @ © 17000%
1700 - 0%
- Unit 1
- Unit 1 must be selected prior to running the calcualtion
- The Calculate ECP"
- 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 END TASK TASK STOP STOP TIME: _ _ _ __
Admin Admin 113 113 fnl fnl Page 7 of 8 Page7of8 CRITICAL STEP CRITICAL STEP EXPLANATIONS:
EXPLANATIONS:
STEP ##
STEP Explanation Explanation 44 Step is Step is necessary necessary because the candidate because the candidate needs needs to to perform perform this this step step for for the the computer computer to calculate to calculate the the ECP ECP to to determine determine the the expected expected rod rod positions positions for for criticality.
criticality.
Admin Admin 113 113 fnl fnl Page 8 of 8 Page8of8 CANDIDATE CUE CANDIDATE CUE SHEET SHEET (TO BE (TO BE RETURNED RETURNED TO TO EXAMINER EXAMINER UPON UPON COMPLETION COMPLETION OFOF TASK)
TASK)
INITIAL CONDITIONS:
Unit 11 operated from 1/15 -4/3 4/3 at 100% power 4/3 1000 - Forced reactor shutdown is commenced at 10%/hr EFPD = 127
=
Forced Outage" 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 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> from the present time per PT/1 PT/i /A/1103/1 5, Reactivity Balance Procedure.
/A/11 03/15, Print out the calculation once it is complete.
Duke Energy . Procedure No.
Oconee Nuclear Station PT/l/A/1103/o15 PT/ I/A/ll03/015 REACTIVITY BALANCE PROCEDURE (Unit 1) Revision No.
067 Electronic Reference No.
OXOO2WBQ OX002WBQ Continuous Use PERFORMANCE II
- ** ** ** ** ** ** ** ** ** UNCONTROLLED FOR PRINT ** ** ** ** ** ** ** ** ** **
(ISSUED) - PDF Format
PT/i/A/l 103/0 15 PT/l!AIlI03/015 Page2of8 Page 2 of8 Reactivity Balance Procedure
- 1. Purpose 1.1 To calculate the Boron concentration necessary to provide greater than I1% ~KIK
% AK/K 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 11% %
~KlK shutdown margin to perform the Control Rod Drive (CRD) patch verification (for AK/K 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 subcritical 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 11 - Physics Test Manual (PTM), ONEI-0400-55 2.4 Unit 11 - Core Operating Limits Report (COLR), ONEI-0400-50
PT/i/All 103/015 PTll/A/1103/015 Page 33 of Page of88 2.5 2.5 Nuclear Systems Nuclear Systems Directive Directive 304, 304, Reactivity Reactivity Management Management 2.6 Work Process Manual, Work Manual, Section Section 2.5, 2.5, Testing Testing
- 3. Time
- 3. Time Required Two people - 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> for most
- most enclosures
- 4. Prerequisite Tests None
- 5. Test Equipment Personal computer (for computerized calculations)
- 6. Limits and Precautions 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 fl the power history information from the last equilibrium Xe/Sm condition is NOT IF 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 z\KJK). (R.M.)
% ilKlK).
1%
- 7. Required Unit Status None
- 8. Prerequisite System System Conditions Conditions None
PT/i/All 103/0 15 PT/IIAl1103/015 Page4of8 Page 4 of8
- 9. Test Method 9.1 Shutdown Boron Concentration:
Calculated in Enclosure 13.1, Shutdown Boron Concentration/Shutdown Margin 13.2, Computerized Shutdown Margin Calculation.
Calculation, or 13.2, The shutdown Boron concentration provides a greater than 1.0% AX/K shutdown margin 1.0%.6.KIK with the worst case stuck rod assumed to be out.
A reference shutdown Boron concentration is obtained based on the cycle burnup, 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 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. The Shutdown Boron only during that time interval. Due to uncertanities in the Xenon concentration is valid y 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
.L\KlK shutdown margin (i.e., the required Boron concentration for a greater than 1.0% AK/K 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. AK/K is then subtracted from this value to obtain the AK/K. 1.0% .L\KlK AK/K. A separate check for SSF RC Makeup System shutdown margin, expressed in - % .L\KlK.
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/All 103/015 PT/I/A/1103/015 Page of88 Page 55 of shutdown, Control Following a shutdown, Rod Position at the time of Control Rod Shutdown may be used with of Shutdown Limit curves (in COLR) to verify at least Position Limit the Rod Position least 1% ~KlK shutdown margin 1% AKIK for the first 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> following shutdown (provided RCS Temperature stays?: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, 13.1, Shutdown Boron Concentration/Shutdown Margin Calculation, and 13.2, ConcentrationlShutdown 13.2, Computerized Shutdown Margin Calculation) may not show 1% ~KlK shutdown margin immediately after shutdown.
1% AKJK Boration should begin immediately to be able to show 1% ~KlK shutdown margin using 1% AKIK 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: 11%
be?: ~KlK by
% AKIK using the Rod Position Limits curves (in COLR). Operation in the "Acceptable Acceptable Region Region" of these curves ensures that the shutdown margin following a reactor trip will be?: be 2: 11%
~KlK with the worst stuck rod out. There are curves for 3 AK/K 3 and 4 RCP operation, and curves for 0 and 11 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.
burnup. The reactivity worths The core excess reactivity is obtained based on the cycle bumup.
associated with Boron, Xenon, temperature correction (ifRCS(if RCS 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
~KlK. The upper and lower rod position the above, yields a total core reactivity of 0.0% AK/K.
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.
burnup. The reactivity worth The core excess reactivity is obtained based on the cycle bumup.
(if RCS temperature not at 532°F),
associated with Xenon, temperature correction (ifRCS 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% ~KlK. AK/K.
PT/l!Al1103/015 PT/i/All 103/0 15 of 8 Page 6 of8 9.6 Subcritical Sub critical Multiplication Measurement:
Performed in 13.6, Computerized Subcritical Multiplication (11M) (1/M) Measurement.
With Group 11 at 50% wd, an initial source range (SR) count rate (Co) ) is recorded. During 0
(C control rod withdrawals, new counts (C) are recorded and used to calculate 11M, 1/M, or CJc.
/C.
0 C
0o will approach infinity, and 11M C/C As criticality is approached, CIC 1/M will approach zero.
Plotting 11M 1/M 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% AKIK~KJK below the Estimated Critical Position calculated in step 9A.9.4.
- 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.
10.4 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 AK/K shutdown margin.
a 1.0% SK/K 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.
11.4 llA 1/M approach to critical: Criticality is achieved within 0.75% ~kIk Acceptance criteria for 11M Ak/k of the predicted critical rod position concentration.
11.5 Review criteria for 11M 0.35%~k/k of 1/M approach to critical: Criticality achieved within 0.35%Aklk the predicted critical rod position for startups considered Xenon free, 0.5% ~ Ak/k review criteria for non-Xenon free startups.
PT/i/All 103/0 15 PT!l/Al1103/015 Page 7 of8 of 8
- 12. Procedure Complete, or refer to, the appropriate enclosure(s):
Shutdown Margin Calculation while shutdown:
Enclosure 13.1, "Shutdown Shutdown Boron Concentration/Shutdown Margin Calculation,"
Calculation, or Computerized Shutdown Margin Calculation" Enclosure 13.2 "Computerized Calculation Estimated Critical Rod Position:
Computerized Estimated Critical Rod Position Calculation" Enclosure 13.4, "Computerized Calculation Estimated Critical Boron Concentration:
Computerized Estimated Critical Boron Calculation" Enclosure 13.5, "Computerized Calculation Subcritical Computerized Sub (1/M) Measurement:
critical Multiplication (11M)
Computerized Subcritical Multiplication (11M)
Enclosure 13.6, "Computerized (1/M) Measurement" Measurement Refueling Outage Boron Concentrations:
Refueling Outage Boron Concentrations" Enclosure 13.13, "Refueling Concentrations Required Control Rod Group 8 Position:
Required Group 8 Position and Designed Cycle Length" Enclosure 13.14, "Required Length Designed Cycle Length Information:
Required Group 8 Position and Designed Cycle Length" Enclosure 13.14, "Required Length Required Shutdown Margin:
Shutdown Margin Requirements" Enclosure 13.16, "Shutdown Requirements Shutdown Margin Calculation at power:
Shutdown Margin Calculation at Power" Enclosure 13.18, "Shutdown Power RCS Boron Concentration for SSF Operability:
Minimum RCS Boron Concentration to Maintain SSF Operability" Enclosure 13.20, "Minimum Operability
PT/I/AI1103/015 PT/i/A/i 103/0 15 of 8 Page 88 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)
(1/M) Measurement 117 13.7 Core Excess Reactivity vs. Bumup 13.8 Differential Boron Worth vs. Bumup Burnup 13.9 Temperature Coefficient vs. RCS Boron Concentration 13.10 Shutdown Boron Concentration vs. Bumup (Group 11 @ @ 0% wd) 13.11 Shutdown Boron Concentration vs. Bumup Burnup (Group 11 @@ 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
13.4 Enclosure 13.4 PT/liAl1l03/0l5 PT/i/A/i 103/0 15 Computerized Estimated Critical Rod Position Page 11 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.____
S6S:£1f~.11 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/ (N/A A next bullet step)
Separate Verification - Must be performed by a Qualified Reactor Engineer (N/A steps 2.8-2.13 for Separate Verification)
NOTE: 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.
4 2.2 (J?1V/,
IA 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 PTPI server, OAC Log, RO Log, etc.
2.2.2 Attach actual power history (from OAC log, TMS, P1 PI Server, etc.) to this enclosure.
Open RhoCaic.
RhoCalc.
Enclosure 13.4 PT/1/A/11o3/o15 PTil/AI1103/015 Computerized Estimated Critical Rod Position Page 2 of 4 Calculation NOTE: beginning of the power history",
- 1. EFPD input into the code shall correspond to the "beginning history, NOT the EFPD effective time of calculation".
at the "effective 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.0CC.
- 3. The ECP time shall run sufficiently into the future to determine if MODE 2 entry could occur with Group 5 < <0%.
0%. This time of occurrence is required in step 2.7 BoronlTemperature) at the time of criticality may be
- 4. Estimated conditions (i.e. RCS Boron/Temperature) used.
s;;SacJ 2.4 Input appropriate data for the estimated critical rod position calculation, select Calculate ECP",
"Calculate ECP, and print.
G", J 0+ -tctS Jc.
2.5 Circle the appropriate response:
Were estimated conditions used for the ECP? Yes/No YeslNo 2.6 Verify Separate Verifications agree on the ECP within 5%wd for all future time steps that have an ECP prediction.
Enclosure Enclosure 13.4 13.4 PT!l/A11103/015 PT/i/All 103/015 Estimated Critical Computerized Estimated Computerized Critical Rod Position Rod Position Page of 44 Page 33 of Calculation Calculation CAUTION:
CAUTION: 1. All safety
- 1. Rods (Groups safety Rods (Groups 1-4) fully withdrawn prior to the time that "Rod 1-4) must be fully Rod Posn @ Mode 2 Entry" column reaches Group 55 <<0%.
Entry (T.S. 3.1.5) column 0%. T. S. S. 3.1.5 3.1.5 entering Mode 2 (Keff> 0.99, SDM prohibits entering SDM <1 <1%% dKlK) dK!K) on the Safeties. IF Groups 11 - 44 can Groups - can NOT NOT be fully withdrawn prior fully withdrawn prior to to the the "Rod Rod Posn @ @ Mode Mode 2 Entry (T.S.
Entry" (T.S. 3.1.5) column indicating 3.1.5) column indicating 55 <<0%, any in-progress 0%, any in-progress approach approach to critical 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 maymaybe N/Aed because the T.S. 3.1.5 limit will NOT be reached AND be N/A'ed Mode 2 (Keff> 0.99, SDM <1 <1% dKJK) will NOT be entered on the Safeties.
% dKlK) 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.
OR 2.7.2 Document the time/date of the time step immediately prior to the first occunence of"5 occurrence of5 <<0% Rod Posn @ Mode 2 Entry" 0%" in the "Rod 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 of ECP with the Control Room SRO. (N/A this step on separate verification calculation).
- - - - - - - - - - - - - - -Control Room SRO 2.9 Attach results of ECP to the procedure and turn ofECP tum the package over to the Control Room SRO. (N/A this step on separate verification calculation).
2.10 2.10 Fill in the actual critical rod configuration and notification limit check on the computer printout. (N/A (NIA this step on separate separate verification calculation).
NOTE:
NOTE: The The notification notification lines of 1/M.xls lines of lIM.xls spreadsheet spreadsheet are are the review review and acceptance criteria criteria of of 11.4 and 11.5.
11.4 and 11.5. IF these criteria are these criteria are NOT met see the met see the WPM WPM section section 2.5, 2.5, Testing, Testing, Approach to to Critical Rod Position.
Critical Rod Position.
2.11 2.11 Verify Verify actual actual critical conditions are critical conditions 1/M.xls notification lines.
are within 1/M.xls (NIA this step lines. (N/A step on on separate separate verification verification calculation.)
calculation.)
Enclosure 13.4 Enclosure 13.4 PT/hAil 103/015 PT!l/A/1103/015 Computerized Estimated Computerized Estimated Critical Critical Rod Position Page Rod Position Page 44 of of 44 Calculation Calculation NOTE:
NOTE: code is ONO3CV.
The Reactor Engineering mail code ON03CY.
2.12 Forward the completed enclosures and attachments, to completed ECP, including all applicable enclosures Engineering. (N/A this step on the separate verification calculation.)
Reactor Engineering. calculation.)
NOTE: "Procedure Completion Approved The GO Nuclear Design Group requires the Procedure Approved" blank to signed off prior to transmittal.
be signed 2.13 Transmit copy of completed ECP to GO Nuclear Design. (N/A this step on separate verification calculation.)
Admin Admin 117 117 fnl fnl Page Page 11 of of 99 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin 117 6620 o~i 2O OJL-Evaluate SSF-ASW operability based on Pressurizer Relief Valve leakage CANDIDATE EXAMINER
Admin 117 fnl Page 2 of 9 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:
Evaluate SSF-ASW operability based on Pressurizer Relief Valve leakage Alternate Path:
No Facility JPM #:
NEW KIA Rating(s):
System: GEN KIA:
K/A: 2.1.7 Rating: 4.4/4.7 Task Standard:
01001 (Reactor Coolant Leakage) Attach. 13.5 (pzr PTI2IA/06101001 Perform PT/2/A/061 (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 PT!2!A/06101001 (Reactor Coolant Leakage) Attach. 13.5 (pzr (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 COMM ENTS
Admin 117 fnl Page3of9 Page 3 of 9 SIMULATOR OPERATOR INSTRUCTIONS:
None
Admin Admin 117 117 fnl fnl Page Page 44 of of 99 Tools/Equipment/Procedures Needed:
Tools/Equipment/Procedures Needed:
PT/2/A/061 0/001 (Reactor PT/2/A/06101001 (Reactor Coolant Coolant Leakage)
Leakage) Attachment 13.5 13.5 (pzr (Pzr Relief Relief Valve Leakage Calculation)
Leakage Calculation)
READ TO OPERATOR DIRECTION TO TRAINEE:
II 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. II 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 II provided you.
INITIAL CONDITIONS:
PT/2/A/0610/001 (Reactor Coolant Leakage) is in progress PT/2/A/06101001 Pzr Relief Valve leakage exists Autolog is NOT available Unit 2 Pzr Steam Space Leakage Excel Calculation NOT available PT!2/A10610/001 (Reactor Coolant Leakage) Attachment 13.5 (pzr PT/2/A/06101001 (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 13.5 (Pzr (pzr Relief Valve Leakage Calculation) and determine SSF ASW Pump operability. Begin at Step 5.6.
Refer to attached data sheet
Admin 117 fnl Page 5 of 9 Page5of9 STARTTIME:
START TIME: _ __
STEP 1: Step 5.6 and 5.7 CRITICAL STEP Perform the following to obtain the Pzr Relief valve Leak Rate ...
Rate...
- SAT STANDARD: Candidate will perform calculation and determine that Pzr Steam Space Leakage=O.18 gpm (0.16-0.20)
Leakage=O.18gpm (0.160.20)
- UNSAT UN SAT Note: Refer to attached key.
Continue to Step 5.8 COMMENTS:
STEP 2: Step 5.8 CRITICAL STEP Determine SSF ASW Pump operability:
- Refer to TS Bases 3.10.1 to determine required Pzr heaters/Pzr heaters!Pzr leakage. - UNSAT 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 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 117 117 fnl Page6of9 P age 6 0 f 9
- CRITICAL
- CRITICAL STEP STEP 3: Step 595.9 IF SSF ASW System is inoperable due to excessive steam space leakage, perform the following:
- SAT
- Enter TS 3.10.1 Condition A
'A' for SSF ASW System inoperability.
inoperability .
- IF required, notify SPOC to restore Pzr Heaters per IPIO!B10200/037 IP/O/S/02001037 UNSAT (Pressurizer Heater Test and Surveillance).
STANDARD: *Determine
- Determine that TS 3.10.1 Condition A 'A' for SSF ASW System inoperability must be entered and SSF ASW must be returned to service within 7 days.
1P101B102001037 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.
U NSAT UNSAT COMMENTS:
END TASK STOP TIME: _ _ _ __
Admin 117 117 fnl Page 77 of 99 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, l&E, number of Bank 2, Group B B & C Pressurizer Heaters available =
= 16
Admin 117 117 fnl ml Page 8 of 99 CRITICAL STEP EXPLANATIONS:
STEP # Explanation 11 Calculation required to determine SSF ASW Pump operability 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
Admn 117 Admin 117 fnl fnl Page9of9 Page 9 of 9 CANDIDATE CUE CANDIDATE CUE SHEET SHEET (TO BE (TO BE RETURNED RETURNED TO TO EXAMINER EXAMINER UPONUPON COMPLETION COMPLETION OF OF TASK)
TASK)
INITIAL CONDITIONS:
INITIAL PT/2/A10610/OO1 PT is in 121A/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!0610!OO1 (Reactor Coolant Leakage) Attachment 13.5 (pzr PT/2/A/06101001 (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 (Pzr Relief Valve Leakage Calculation) and determine SSF ASW Pump operability. Begin at Step 5.6.
Refer to attached data sheet
Enclosure 13.5 Enclosure PT/2/A/0600/OlO PT 121A/060010 10 Pzr Relief Valve Leakage Calculation Page 11 of9 of 9
- 1. Initial Conditions
~1.l1.1 Verify RCS Temperature AND Pressure stable. {17}
{ 1 7}
- 2. Procedure {3} {3}
2.1 y RCP Seal Leakage Flow indicator is out of service, perform the following:
IF any JV/~Y.l.l1 Notify Systems Engineering.
Person Notified Date 2.1.2 N/A NI A remainder of this enclosure.
t.Q:J 2.2 { 14}
Ensure weekly pressurizer boron sample has been requested. {14}
NOTE: Pzr Steam Space Leakage Excel Calculation available on OPS Web Page.
JV Iflty~.3 IF Unit 2 Pzr Steam Space Leakage Excel Calculation available, perform Section 33 (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:
~.4.11 Of RCP Seal Leakage Flow Trend History).
Refer to Section 4 (Example OfRCP 2.4.2 Perform Section 5 (Unit 2 Pzr Steam Space Leakage Excel Calculation NOT Available).
13.5 Enclosure 13.5 PT/2/A10600/OlO PT/21 A/060010 10 Leakage Calculation Pzr Relief Valve Leakage Calculation Page 2 of9 of 9
- 3. Unit 2 Pzr Steam Space Leakage Excel Calculation available 3.1 Use Unit 2 Pzr Stearn Steam 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} {11}
- 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 heaters/Pzr leakage.
3.3 IF SSF ASW System is inoperable due to excessive stearn j steam space leakage, perform the following:
3.3.1 Enter TS 3.10.1 Condition 'A' EnterTS A for SSF ASW System inoperability.
3.3.2 IF required, notify SPOC to restore Pzr Heaters per IP/O/B/02001037 IP/0/B/0200/037 (Pressurizer Heater Test and Surveillance).
3.3.3 Notify System Duty Engineer.
3.4 Record Unit 2 Pzr Stearn Steam Space Leakage in Autolog.
Enclosure 13.5 PT121Al0600lO 110 PT/2/A/0600/0 0 Pzr Relief Valve Leakage Calculation Page 3 of9 of 9 RCP Seal Leakage Flow Trend History
- 4. Example Of Rep
- HISTORY ** GROUP TREND ** HISTORY **
4.0 4.0 ,--------------~-------------.
3.5 3.0 2.5 2.0 1.5 1.0 0.5 0.0 -,-'-rl---,-,-----,-'-,-----,-----,'-----,-----,-----,----J~~"___,_--,___'r=r=r' 11:37:25:63 11 :37:25:63 11:39:36:93 11 :39:36:93 11:41:52:23 11:41 :52:23 11 :44:05:53 11:44:05:53 Seat Seal leakage flow r2.tcw rtr 8104/05 RCP Rep SEAL LEAKAGE FLOW
Enclosure 13.5 PT/2/A/0600/Ol0 PT121A/0600/0 10 Pzr Relief Valve Leakage Calculation of 9 Page 4 of9
- 5. Unit 2 Pzr Steam Space Leakage Excel Calculation NOT available {IS} {15}
5.1 Perform ~one of the following to obtain 2A1 RCP Seal Leakage Flow:
~ IF 2A1 RCP Seal Leakage Flow (CP 02A1938) 2 0.30 gpm, m, record indicated value below and in Step 5.5:
55:
2A1 RCP Seal Leakage Flow: _ _ _ _ _ _ gpm 02A 1938) <
IF 2A1 RCP Seal Leakage Flow (CP 02A1938) m AND Time Trend/History 0.30 gpm
<0.30 for 2A1 RCP Seal Leakage Flow (CP 02A1938) indicates < <22 dumps in the past hour, record 0.0 gpm for 2A1 RCP Seal Leakage Flow in Step 5.5:
2Al RCP Seal Leakage Flow: _ _..;;.O~.O::.-_
0.0 gpm
- 2A1 RCP Seal Leakage Flow (CP 02A1938) < 0.30 gpm AND Time Trend/History IF 2Al for 2Al 2A1 RCP Seal Leakage Flow (CP 02A1938)
O2Al938) indicates 2 2 dumps in the past hour, perform the following:
Trend/History:
A. Calculate flow rate using Time TrendlHistory:
~ 1. Record Time #1 2A1 RCP Seal Leakage Flow (CP 02A1938):
04: otot>~ 00 HH:MM:SS
~ 2. Record Time #2 2A1 RCP Seal Leakage Flow: (CP 02A1938): O2Al938):
Olf.2':CO cc HH:MM:SS
~ 3. Record Time ##11 to Time #2 Duration: Li 40 II seconds
~. 4)4. 2A1 RCP Seal Leakage Flow:
Calculate 2Al (0.29 +÷ lL J
-.1 40 Leg sec) (60) ==
sec)(60) O.
O 0c) Ij gpm (Duration) (2A I Rep (2Al RCP Seal Leakage Flow)
Record indicated value below and in Step 5.5:
2A1 RCP Seal Leakage Flow: O.
(X 0 I.) I1 gpm
Enclosure 13.5 PT/2/A10600/0l0 PT121Al060010 10 Pzr Relief Valve Leakage Calculation Page 55 of9 of 9 5.2 Perform one of the following to obtain 2A2 RCP Seal Leakage Flow:
- J0rm.!!.ill
/I/}/I- 02A 1940) ~ 0.30 gpm, record indicated value IF 2A2 RCP Seal Leakage Flow (CP 02A1940) below and in Step 5.5:
2A2 RCP Seal Leakage Flow: _ _ _ _ _ _ gpm
- 02A 1940) <
IF 2A2 RCP Seal Leakage Flow (CP 02Al940) <0.30 0.30 gpm AND Time Trend/History 02A 1940) indicates < 2 dumps in the past hour, for 2A2 RCP Seal Leakage Flow (CP 02Al940) record 0.0 gpm for 2A2 RCP Seal Leakage Flow in Step 5.5:
2A2 RCP Seal Leakage Flow: _ _..:;.O.:..;.O~_
0.0 gpm
-* 02A 1940) <
IF 2A2 RCP Seal Leakage Flow (CP 02Al940) <0.30 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 V
I 940):
04: 00:00 HH:MM:SS cJ
~ 2. Record Time #2 2A2 RCP Seal Leakage Flow: (CP 02Al940): 02A 1940):
o-f OJ:
Olf: oJL49lf9 HH:MM:SS
~. Record Time #1 to Time #2 Duration: _ .....l'-'O09
""--9-L--____ seconds
~ 4. Calculate 2A2 RCP Seal Leakage Flow:
(0.29 ÷ (0.29+ loG) p9 sec) (60) =
sec)(60) = 0.
(). i, to L lo gpm (Duration) (2A2 RCP Rep Seal Leakage Flow)
)
~. Record indicated value below and in Step 5.5:
2A2 RCP Seal Leakage Flow: 0. l1 to O. t.o gpm
Enclosure 13.5 PT/2/A/0600/0l0 PT121A/060010 10 Pzr Relief Valve Leakage Calculation of 9 Page 6 of9
- '~3Aj 5.3 Perform ~one of the following to obtain 2BI 2B1 RCP Seal Leakage Flow
AYiA.A. 2B1 RCP Seal Leakage Flow (CP 02A1939) ~ 0.30 gpm, record indicated value IF 2Bl below and in Step 5.5:
2B11 RCP Seal Leakage Flow: _ _ _ _ _ _ gpm 2B 2B1 RCP Seal Leakage Flow (CP 02A1939) < 0.30 gpm AND Time Trend/History IF 2Bl 2B1 RCP Seal Leakage Flow (CP 02A1939) for 2Bl 02A 1939) indicates < <22 dumps in the past hour, 2B1 RCP Seal record 0.0 gpm for 2Bl Leakage Flow in Step 5.5:
2B 0.0 2B11 RCP Seal Leakage Flow: _ _..;;.0..;.;.0;;...-._ gpm
- IF 2Bl 02A 1939) < 0.30 gpm AND Time Trend/History 2B1 RCP Seal Leakage Flow (CP 02A1939) 02A 1939) indicates ~ 2 dumps in the past hour, 2B1 RCP Seal Leakage Flow (CP 02A1939) for 2Bl perform the following:
A. Calculate flow rate using Time Trend/History:
~ 11 1.
c
) Record Time #1 2BI2B1 RCP Seal Leakage Flow (CP 02AI939): 02A 1939):
OU:oO:oD OLE 00o0 HH:MM:SS
~2.2. Record Time #2 2BI2B1 RCP Seal Leakage Flow: (CP 02A1939): 02A 1939):
oLr.\4:30 HH:MM:SS 1h!.
~4.4.
Record Time #1 to Time #2 Duration:
2B11 RCP Seal Leakage Flow:
Calculate 2B 0
_--=f?_I-'--"O=--___ seconds (0.29 +
÷ ~ 70 7Q sec) (60) = = O*
- 0. 002 "2- gpm (Duration) (2B1 Rep (2BI RCP Seal Leakage Flow) cl,)B. Record indicated value below and in Step 5.5:
2B11 RCP Seal Leakage Flow:
2B (3 Q:L O. 0 1. gpm
Enclosure 13.5 Enclosure 13.5 PTI2/A/0600 PT 121Al0600/0 10l0 10 Pzr Relief Pzr Valve Leakage Relief Valve Leakage Calculation Calculation Page 7 of9 Page 7 of 9 5.4 Perform ~
Perform one of following to the following of the to obtain obtain 2B2 2B2 RCP RCP Seal Seal Leakage Leakage Flow:
Flow:
M.
in Step 5.5:
Flow (CP 02A1941)
(CP 02A194l) ~ 0.30 gpm, record 0.30 gpm, record indicated indicated value value 2B2 RCP 2B2 RCP Seal Leakage Flow:
Seal Leakage Flow: _ _ _ _ _ _ gpm gpm di.IA
Seal Leakage Flow (CP 02Al941)
Flow (CP 02Al941)
<0.30 0.30 gpm AND Time Trend/History indicates <
02A1941) indicates Trend/History
<22 dumps in the the past hour, record 0.0 gpm for 0.0 gpm for 2B2 RCP RCP Seal Seal Leakage Flow in in Step Step 5.5:
5.5:
0.0 2B2 RCP Seal Leakage Flow: _ _..;;.0,;..;.0:...-_ gpm
Trend/History:
A. Calculate flow rate using Time Trend/History:
¥ 1. Record Time #1 2B2 RCP Seal Leakage Flow (CP 02AI94l): 02A1941):
HH:MM:SS
~ 2. Record Time #2 2B2 RCP Seal Leakage Flow: (CP 02AI941): 02A1941):
HH:MM:SS
~3. 3. Record Time ##11 to Time #2 Duration: - - 3 - - - seconds Ll-::3
~4. 4. Calculate 2B2 RCP Seal Leakage Flow:
(0.29 (0.29+ ÷ 4'6S S sec) (60) sec)(60)= O.oLl
- 0. D 1.4 gpm (Duration) (2B2 RCP Rep Seal Leakage Flow)
~ Record indicated value below and in Step 5.5:
2B2 RCP Seal Leakage Flow: D. p
(. 0 Lj4 gpm
Enclosure 13.5 PT/2/A/0600/OlO PT 121Al060010 10 Pzr Relief Valve Leakage Calculation of 9 Page 8 of9 5.5
¥-5.5 Sum individual RCP Seal Leakage Flows to determine Total RCP Seal Leakage Flow:
2A1 RCP Seal Leakage Flow:
2AI 0. o I 0.01 gpm 2A2 RCP Seal Leakage Flow: o.
- 0. lio
) to gpm 2B11 RCP Seal Leakage Flow:
2B (9- 0).
O~Ol gpm 2B2 RCP Seal Leakage Flow: Q. 0( 4-O. 11- gpm Total RCP Seal Leakage Flow: 0. 2.. 3 0.23 gpm 5.6 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/inch == gals (QTLevel (QT Level Change) (QT Volume Change) 5.6.3 Calculate QT Volume Change Rate:
_ _ _ _ _ _ _ gals +÷ _ _ _ _mIll mm = = gpm (QT Volume Change) (Duration) (QT Volume Rate) 5.7 Calculate Pzr Steam Space Leakage:
_ _ _ _ _ _ gpm gpm-- gpm gpm= = gpm Volu,ne Rate)
(QT Volume (Total RCP Seal Leakage Flow) (pzr (Pzr Steam Space leakage) 5.8 Determine SSF ASW Pump operability: {II} {1 1 }
- 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 heaters/Pzr leakage.
Enclosure 13.5 Enclosure 13.5 PT 121Al060010 10 PT/2/A/0600/O1O Pzr Relief Pzr Relief Valve Valve Leakage Leakage Calculation Calculation Page Page 99 of9 of 9 5.9 5.9 IF SSF IF SSF ASW ASW System inoperable due System isis inoperable due to excessive steam to excessive steam space space leakage, leakage, perform perform the the following:
following:
- Enter TS 3.10.1 Enter 3.10.1 Condition 'A' A for for SSF SSF ASW ASW System System inoperability.
inoperability.
- IF required, notify IF notify SPOC SPOC to Pzr Heaters to restore Pzr Heaters per IP/O/BI02001037 TP/OIB/0200/037 (Pressurizer (Pressurizer Heater Test and Surveillance).
- System Duty Engineer.
Notify System 5.10 Record Unit 2 Pzr Steam Space Leakage in Autolog.
Enclosure 13.5 PT/2/A/0600/01O PT121A/0600/o 10 Pzr Relief Valve Leakage Calculation Page 88 of of99 2L- 5.5 Sum individual RCP Seal Leakage Flows to detemine detennine Total RCP Seal Leakage Flow:
2A 1 RCP Seal Leakage Flow:
2A1 04 O l 0.0 I gpm 2A2 RCP Seal Leakage Flow: C).. to I (, gpm 2B 1 RCP Seal Leakage Flow:
2B1 6*o~
. gpm 2B2 RCP Seal Leakage Flow: ",6f C f gpm Total RCP Seal Leakage Flow: 0 3 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:
~()n ~O. 0
.O = o7 (Final QT level) (Initial QT level) (QT level Change) 5.6.2 L5.6.2 Convert QT Level Change to gallons: {4}
C2.~ inches x 34.94 galslinch gals/inch == ) ~ 4.
- 4. if14 S &
S &> gals Level Change)
(QTLevel (QT (QT Volume Change)
Change,)
5.6.3 Calculate QT Volume Change Rate:
L Lj$.%
1-~. L/~8, (QT Volume Change) gals +÷ '0 (Duration) mm ==
min O*l{ f (QT Volume Rate) gprn gpm L5.7 Calculate Pzr Steam Space Leakage:
6 r 41 gpm - - 0 f3 0 I gpm == O.. I1 A 0 gpm (QT Volume Rate) (Total RCP Seal Leakage Flow) (pzr(Pzr Steam Space leakage) 5.8 Determine SSF ASW Pump operability: {II} {ll}
- Refer to Autolog or contact I&E to determine operable SSF Pzr Heaters.
- determine required Pzr heaters/pzr Refer to TS Bases 3.10.1 to detennine heaters/Pzr leakage.
Admin-203 fnl Admin-203 fnl Page 11 of Page of 77 REGION II EXAMINATION INITIAL LICENSE EXAMINAT ION PERFORMANCE JOB PERFORMA NCE MEASURE Admin-203 1D OAJtf Sf2D Complete Plant Configuratio Configurationn Sheet (Time to Core Boil)
CANDIDATE EXAMINER
Admin-203 fnl Admin-203 fnl Page Page 22 of of 77 REGION REGION IIII INITIAL LICENSE EXAMINATION INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE Task:
Complete Plant Complete Plant Configuration Sheet Sheet (Time (Time to Core Core Boil)
Boil)
Path:
Alternate Path:
No No Facility JPM Facility JPM #:
Admin 203 203 KIA Rating(s):
K/A System: GEN KIA:
K/A: 2.2.18 Rating: 2.6/3.9 Task Standard:
OP/U/Ni 108/001 are used to determine Total Loss Of DHR Time to Boil Tables in OP/O/A/1108/001 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant Perform X Simulate
References:
OP/O/A/1108/001 OP/U/Ni 108/001 (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
Admin-203 Admin-203 fnl fnl Page Page 33 of of 77 SIMULATOR OPERATOR INSTRUCTIONS:
SIMULATOR OPERATOR INSTRUCTIONS:
Admin-203 fnl Page 4 of 7 Tools/Equipment/Procedures Needed:
ToolslEguipment/Procedures OP/0/A/1108/001 OP/0/A/1 108/001 (Curves and General Information) Enclosure 4.46 (Total Loss of DHR Time to Boil)
READ TO OPERATOR DIRECTION TO TRAINEE:
II 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. II 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 II provided you.
INITIAL CONDITIONS:
- Unit 1 onl2/01 0400 1 was shutdown on12/01
- 1 .3.5 (Shutdown Protection Plan) Attachment 9.2.A is being prepared for this Site Directive 1.3.5 shift.
INITIATING CUES:
Current Date/Time: 12/04 0600 The SRO instructs you to calculate the "Time Boil and perform any required actions Time To Core Boil" based on the calculation results in accordance with Site Directive 1.3.5 1 .3.5 (Shutdown Protection Plan) Attachment 9.2.A.
Admin-203 fnl Page 5 of 7 Page5of7 STARTTIME:
START TIME: _ __
STEP 1: OP/0/AIl 108/001 Refer to enclosure 4.46 of OP/0/Al110S/001 CRITICAL STEP Choose the appropriate table
- SAT STANDARD: Refer to enclosure 4.46 of OP/O/Al11 OS/001 and use the "Prior OPIOIAI1 108/001 Prior to Refueling - Initial Temp =
- S/D); Time to Boil in
= 110°F (Hours Since SID);
Minutes" Minutes table. UNSAT COMMENTS:
STEP 2: Determine the number of hours the reactor has been shutdown. CRITICAL STEP
- SAT STANDARD: Determine the reactor has been shut down for 74 Hours.
COMMENTS:
- UNSAT STEP 3: Determine time to boil. CRITICAL STEP STANDARD: Determine time to boil is 20.9 minutes by using 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> and SO 80 SAT inches on L T-5.
LT-5.
COMMENTS:
- UNSAT U N SAT STEP 4: Ensure SPOC is manning equipment hatch
- SAT STANDARD: Ensures SPOC is manning equipment hatch since Configuration Sheet indicates that Equipment Hatch is Open COMMENTS: UNSAT END TASK STOP TIME: _ _ _ __
Admin-203 fnl Admin-203 fnl Page Page 66 of of 77 STEP EXPLANATIONS:
CRITICAL STEP STEP #
STEP Explanation Explanation 11 to determine Required to core boil.
determine the time for core boil.
22 determine the time for core boil.
Required to determine 33 Required to determine the time for core boil.
Admin-203 fnl Page 7 of 7 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- Unit 1 I was shutdown on12/01 onl2IOl 0400
- 1 .3.5 (Shutdown Protection Plan) Attachment 9.3.A is being prepared for this Site Directive 1.3.5 shift.
INITIATING CUES:
12/04 0600 Current Date/Time: 12/040600 Time To Core Boil" The SRO instructs you to calculate the "Time Boil and perform any required actions based on the calculation results in accordance with Site Directive 1.3.5 1 .3.5 (Shutdown Protection Plan) Attachment 9.2.A.
Attachment 9.2.A Attachment 9.2.A - Plant
- Configuration Sheet Plant Configuration Sheet Unit I1 Unit Mode:
Mode: 66 Preparer:
Preparer: Date:
Date: TODAY TODAY Time:
Time: 4:00 4:00 Reviewer:
Reviewer: Date:
Date: Time:
Time:
RCS Level:
RCS Level: 80 in.
80 in. As Reed As Read On:
On: LT-5 LT-5 RCS Temperature:
RCS Temperature: 110 °F 110 of As Read As Read On:
On: LPIP LPIP Suction Suction RCS Level RCS Level Control Control Band:
Band: 84 in.
84 in. (High) 62 62 in.in. (Low)
(Low) Temperature Band:
RCS Temperature RCS Band: 125 °F 125 of (High)
(High) 90 °F 90 of (Low)
(Low)
Operable: A I W BB W C P C W Pumps Operable LPSW Pumps LPSW Operable A 1 W BB W C f C W LPI Pumps LPI Pumps Coolers:
Coolers: A l A W BB I W LPSW Suction LP5W From Unit:
Suction From Unit: 22 CCW CCW SF Pumps SF Pumps Operable:
Operable: A A lW BB I W C l C W RCW Pumps RCW Pumps Available:
Available: A 1 W BB 1 W C W C f DD 1W SF Coolers SF Coolers Operable:
Operable: A W BB I W C W C Coolers Available RCW Coolers RCW A J W BB P W C C [ W DD 1W SFP Level:
SFP 0.18 ft.
0.18 SFP SFP Temperature Temperature 71 of 71 Level Control Band:
Level Band: -2
-2 ft. To i1 ft. Time For SFP Temperature to Reach 210 For SFP °F:
210°F: >66
>66 hours FTC Flooded FTCFlooded YES F r NO W 1 ReactorVesselHead Reactor Vessel Head OFF F r ON 1 W
LP-1 ~ump Path 9 Sump Lr'-l~ r'am Available AvaliaOle (Flange on wI (t-Iange oft wi Fuel in Reactor Vessel YES W P NO r F No Red Tags on LP-19) YES W W NO r F
Lr'-,W Sump LP-20 :sump Path (!-Iange off r'atn Available (Flange ott w/
wi YES rF Operable CETCs CETC5 SOME List: G6, F7, F8, H9, Gil G11 No Red Tags on LP-20) NO W[
Time To To Core Boil Minutes Reactor Bldg Purge is: OFF W1 ON rF
~ 16 mm.
If Time to Core Boil is <16 min. ensure equipment hatch is closed. Equipment Hatch is: cLosso CLOSED IF OPEN W If Time to Core Boil is << 30 min. mm. ensure SPOC SP~C is manning equip. hatch if open. SPOC is manning Equip. Hatch: YES rF NO rF RCS Makeup Paths A OTSG AOTSG B OTSG BOTSG W BHUT --> HP-363 --> A / B LPI BHUT>HP-363-->A/BLPI ABHUT 57,071 GAL. UpperPrimaryHandholes Upper Primary Handholes ON W OFF IF ON j OFF W rF w BWST --> A / B LPI (Forced BWST-->A/B / Gravity)
(Forced/Gravity) BWST 377,146 GAL. Upper Primary Manways ON W f OFF rF ON w r OFF rF wf BWST BWST // BHUT -->--> A HPI -->
--> HP-410 CBAST 4,770 GAL.
YES rF NO rF YES rF NO w J
IF BWST BWST // BHUT -->--> B HPI -->
--> HP-409 OTSG Nozzle Dam Installed RCS Boron:
RCS 2750 (Actual) 675 (Required) Cold Legs Are: DRAINED DRAINED rF NOT DRAINED W*
Canal Canal Seal Seal Plate:
Plate: ON ON WP OFF OFF rF SF-i SF-1 OPEN rF CLOSED CLOSED WP Transfer Tube Covers TransferTube Covers ON W OFF rF SF-2 OPEN rF CLOSED W P OFFSITE POWER SOURCES Main Feeder Main Bus ##11 Feeder Bus Energized Energized YES P W NO rF CT-i IF CT-1 CT-2 rF CT-3 IF CT-3 BACKCHARGED BACKCHARGED MAIN MAIN TRANSFORMER TRANSFORMER W Main Feeder Main Bus ##2 Feeder Bus 2 W
Energized Energized YES W YES W NO NO rF CT-5 CT-5 (From (From Central Central Switchyard)
EMERGENCY EMERGENCY POWER POWER SOURCESSOURCES CT-i W CT-1 P CT-2 rF CT-2 CT-3 rF CT-3 Installed on RC-66 Installed RC-66 on PZR PZR YES YES rF NO NO wF CT-4 W CT-4 1 RC-67 Installed RC-67 on PZR Installed on PZR YES YES rF NO NO w[
CT-5 CT-5 (From (From Lee Lee Combustion Combustion Turbine Turbine via via Isolated Isolated Power Power Path)
Path) IF RC-68 Installed RC-68 on PZR Installed on PZR YES YES rF NO NO W l NOTES:
NOTES:
Attachment 9.2.A -- Plant Configuration Sheet Unit 1 I Mode: 6 Preparer: Date: TODAY Time: 4:00 Reviewer: Date: Time:
RCS Level: in.
80 in. As Read On: LT-5 RCS Temperature: 110 of°F As Read On: LPIP Suction RCS Level Control Band: 84 in. (High) 62 in. (Low) RCS Temperature Band: 125 of°F (High) °F (Low) 90 of LPI Pumps Operable: A Fl P B j7 P C j7 LPSW Pumps Operable A P j7 B P B j.;i C P LPI Pumps Coolers: A pc P B B P R LPSW Suction From Unit: 2 CCW SF Pumps Operable: A R:
P B W f C
~.
RCW Pumps Available: A W P B W B P C f;1 P D P SF Coolers Operable: A R:
P B P W C R RCW Coolers Available A W P B P B j'" C W P D W P
SFP Level: 0.18 ft. SEP Temperature SFP 71°F 71 Level Control Band: -2 ft. To 1 ft.
1 Time For SFP Temperature to Reach 210 OF: °F: >66 hours FTC Flooded YES r:
F NO W P Reactor Vessel Head OFF rF ON RP LP-I9 Sump Patti Lt-'-l~ ~ump Available (Flange Oil t-'arn AvaliaOle(t"lange off WI wI Fuel in Reactor Vessel YES j7 P NO rF No Red Tags on LP-19)
Na YES W P NO ir-j LP-20 Lt-'-lU Sump Path
~ump Available (t"lange t-'arn AvallaOle (Flange all off wI WI Operable CETCs SOME List: G6, F7, F8, H9, G11 Gil NoRedTagsonLP-20)
No Red Tags on LP-20) YES rF NO NO P I'"
Time To Core Boil Minutes Reactor Bldg Purge is: OFF W P ON r-F If Time to Core Boil is ~ mm. ensure equipment hatch is closed.
< 16 min. Equipment Hatch is: ccoseo CLOSED rF OPEN W P
If Time to Core Boil is < < 30 min.
mm. ensure SP~C SPOC is manning equip. hatch if open. SPOC is manning Equip. Hatch: YES r--
F NO rF RCS Makeup Paths A OTSG AOTSG B OTSG BOTSG v7 BHUT SHUT -->
--> HP-363 -->--> A I B B LPI A BHUT ABHUT 57,071 GAL. Upper Primary Handholes ON [.;;'
P. OFF r~
F ON p OFF rF P'
r--
Wp BWST -->--> A AlI B B LPI (Forced (Forced!I Gravity) BWST 377,146 GAL. Upper Primary Manways ON p; P OFF rF ON W P OFF !F r;t BWST!I BHUT 7 BWST SHUT --> HPI --> HP-410
--> A HPI--> CBAST 4,770 GAL.
YES F NO F YES rF NO P-1"'
rF BWST BWST!I BHUT -> > BB HPI-->
HPI > HP-409 HP409 OTSG Nozzle Dam Installed RCS Boron: 2750 (Actual) 675 (Required) Cold Legs Are: DRAINED rF NOT DRAINED W' P
Canal Seal Plate: ON R P OFF rF SF-i SF-1 OPEN rF CLOSED W P
Transfer Tube Covers TransferTube ON R" P OFF ,Fr SF-2 OPEN ri: CLOSED R P
OFFSITE POWER SOURCES Main Feeder Bus # #11 I"""'
Energized YES P 57 NO rF CT-i CT-1 F C CT-2 F CT-3 tF ... ,
BACKCHARGED MAIN TRANSFORMER P Main Feeder Bus # #22 Energized YES po p NO rF CT-5 CT-S (From Central Switchyard) R P
EMERGENCY POWER SOURCES CT-i CT-1 pc P CT-2 r:F CT-3 rF RC-66 Installed on PZR YES F r NO P P'
CT-4 P j7 RC-67 Installed on PZR YES rF NO w P
CT-5 (From Lee Combustion Turbine via Isolated Power Path) rF: RC-68 Installed on PZR YES rF NO R" P
NOTES:
Admin-207 Admin-207 fnl fnl Page 11 of Page of 99 REGION II INITIAL LICENSE EXAMINATION EXAMINATION PERFORMANCE MEASURE JOB PERFORMANCE
_o fGO O,UL(
O,u L 1 Admin-207 Perform SG Downcomer Temperature Surveillance CAN DI DATE CANDIDATE EXAMINER
Admin-207 Admin-207 fnl fnl Page of 99 Page 22 of REGION IIII REGION INITIAL LICENSE INITIAL LICENSE EXAMINATION EXAMINATION JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE Task:
Task:
Perform SG Perform SG Downcomer Downcomer Temperature Surveillance Alternate Path:
Path:
No No Facility JPM Facility JPM #:
New KIA Rating(s):
System: Gen KIA:
K/A: 2.2.12 Rating: 3.7/4.1 Task Standard:
Perform SG Downcomer Temperature Surveillance by procedure for the 1A 1A) SG and 1A (and ONLY the 1A) determine that the surveillance is NOT met.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator _X_X In-Plant _ _ Perform X Simulate
References:
OP/1/A/11 End 4.1 (Mode 1 05/014 Encl OP/1/A/1105/014 &2) and Enc!.
1&2) End. 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 U N SAT _ __ Performance Time: - - - -
Examiner:
Examiner: _________________________
NAME SIGNATURE DATE
========================================================================
COMMENTS
Admin-207 fnl Page 3 of 9 SIMULATOR OPERATOR INSTRUCTIONS INITIAL SETUP SNAP2I2
- 1. Recall SNAP 212
- 2. Import files for Admin 207
- 3. Briefly place simulator in RUN then return to FREEZE SUBSEQUENT SETUP JPMs. Simulator can remain in freeze It is NOT necessary to recall simulator between JPM's.
and only actions below are required.
- 1. Call up different OAC screens than ones required during the JPM
Admin-207 Admin-207 fnl fnl Page 4 of 9 Page4of9 Tools/Equipment/Procedures Needed:
Tools/Equipment/Procedures Needed:
0P111A111051014 (Control OP/1/A/1105/014 (Control Room Room Instrumentation Instrumentation Operation Operation And Information)
Information)
READ TO OPERATOR READ DIRECTION TO TRAINEE:
II 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. II 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 II provided you.
INITIAL CONDITIONS:
Reactor power =100%
0P111A111051014 OP/1/A/11 05/014 (Control Room Instrumentation Operation And Information) Enclosure 4.1 (Mode 1 1 & 2) in progress.
INITIATING CUES:
OP/11A111051014 CR SRO directs you to continue OP/1/A/11 05/014 (Control Room Instrumentation Operation And Information) Enclosure 4.1 (Mode 1 I &
& 2) beginning on page 4.
Admin-207 fnl Page 5 of 9 Page5of9 START TIME: _ __
CRITICAL STEP STEP 1: Verify All SG Downcomer Temperature computer pOints points agree within 3°F of each other.
- SAT IF All SG Downcomer Temperatures DO NOT agree within 3°F of each other, then perform Enclosure "Channel Channel Check Of OTSG Downcomer Temperatures".
Temperatures.
- UNSAT 01 E2008 - 535.4 OF 535.4°F 01 E2009 - 541.3°F 01E2009541.3°F 01E2012 - 535.4°F 01 E2013 E201 3 - 535.4 OF 535.4°F STANDARD: Determine that the above OAC point do NOT agree within 3°F of each other, and perform Enclosure "Channel Channel Check Of OTSG Downcomer Temperatures".
Tern peratures.
COMMENTS:
STEP2:
STEP 2: Step3.1 Step 3.1 Determine saturation temperature for 1 A OTSG based on power level 1A
- SAT and 11AA OTSG outlet pressure as follows:
Step 3.1.1 Determine 1A OTSG outlet pressure using anyone any one of the following
- UNSAT 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 P age 6 0 f9 Page6of9 STEP 3:
3: 3.1 .2 Step 3.1.2 Using table in Section 4, determine the 11AA OTSG saturation temperature power level based on power level and 11 A OTSG OTSG Outlet Pressure Pressure obtained in in step -
SAT 3.1.1.
IA OTSG saturation temperature 1A
- 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 1IA A OTSG saturation temperature determined in instep step 3.1.2: - SAT STANDARD: Determine that 01 E2008 SG Lower Downcomer Temperature Loop A is approximately the same as the 11A A OTSG saturation temperature above. UNSAT COMMENTS:
STEP 5: 3.1 .4 Step 3.1.4 IF 01 E2008 SG Lower Downcomer Temperature Loop A is NOT within of of the 1
+/- 4.9 °F
+/- 1A A OTSG saturation temperature, then enter Condition A - SAT 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 °F of of the 1A 1A OTSG saturation temperature and N/A this step.
COMMENTS:
Admin-207 Admin-207 fnlfnl age 70 PPage 7 off99 STEP 6:
STEP 6: Step 3.1.5 Step 3.1.5 CRITICAL CRITICAL STEP STEP Compare 01 Compare 01 E2009 E2009 SG Lower Downcomer SG Lower Downcomer Temperature Temperature Loop Loop A A to to the the 11A OTSG saturation A OTSG saturation temperature temperature determined determined inin step step 3.1.2:
3.1.2: - SAT SAT STANDARD:
STANDARD: Determine that Determine that 01 E2009 SG 01 E2009 Lower Downcomer SG Lower Downcomer Temperature Temperature Loop Loop A A is is approximately 6°F approximately above 11A 6°F above OTSG saturation A OTSG saturation temperature temperature above above
- UNSAT UNSAT COMMENTS:
COMMENTS:
STEP 7:
STEP 7: Step 3.1.6 Step 3.1.6 CRITICAL CRITICAL STEP STEP IF 01 E2009 SG Lower Downcomer Temperature Loop A is NOT within
+/-
+/- 4.9 of
°F of the 11AA OTSG saturation temperature, then enter Condition A - SAT protection system inoperable.
of SLC 16.7.5 for OTSG overfill protection STANDARD: Determine that 01 E2009 SG Lower Downcomer Temperature Loop A is UNSAT NOT within +/- +/- 4.9 of
°F 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: _ _ _ __
Admin-207 fnl Page 8 of 9 Page8of9 CRITICAL STEP EXPLANATIONS:
STEP # Explanation 11 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 ff1 Page Page 9 of 9 CANDIDATE CUE SHEET (TO BE BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
Reactor power =100%
= 100%
OPI1IA/11051014 OP/1/A/11 05/014 (Control Room Instrumentation Operation And Information) Enclosure 4.1 (Mode 11 & 2) in progress.
INITIATING CUES:
OP/11A11105/014 CR SRO directs you to continue OP/1/A/11 05/014 (Control Room Instrumentation Operation And Information) Enclosure 4.1 (Mode 11 & 2) beginning on page 4.
Enclosure 4.16 Enclosure 4.16 oP/i/All opil IAI 11051014 105/0 14 Channel Check Channel Check OfOf OTSG OTSG Downcomer Page 11 of3 of 3 Temperatures Temperatures
- 1. Limits And Precautions 1.
None
- 2. Initial Conditions E...4 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 1A OTSG based on power level and lA 1A OTSG
- outlet pressure as follows:
SiS-1 1A OTSG outlet pressure using anyone
~ 3.1.1 Determine lA any one of the following computer points:
- 01E2281
- 01E2283
- 01E2031 01E203l
- 01E2032 5\~..-'l 0f-T 3.1.2 Using table in Section 4, determine the lA 1 A OTSG saturation temperature based on power level and 1A lA OTSG Outlet Pressure obtained in step 3.1.1.
335 .3 11 A OTSG saturation temperature
.s~tf 3.1.3 Compare 01E2008 SG Lower Downcomer Temperature Loop A to the lA OTSG saturation temperature determined in step 3.1.2:
~IJttAr 3.1.4 IF 01 E2008 SG Lower Downcomer Temperature Loop A is NOT within 01E2008
+/-+/- 4.9 °F of of the 1AlA OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable.
~u
$$ 3.1.5 3.1.5 Compare Compare 01E2009 SG SG Lower Downcomer Downcomer Temperature Temperature Loop A to the 1A 1A OTSG OTSG saturation temperature determined in step step 3.1.2:
~~§ 3.1.6 jj.
IF 01E2009 SG SG Lower Lower Downcomer Downcomer Temperature Loop A is is NOT within
+/-+/- 4.9 4.9 °F of of of the 1A OTSG saturation temperature, then enter Condition 1A OTSG Condition A of SLC 16.7.5 SLC 16.7.5 for OTSG overfill protection system OTSG overfill protection system inoperable.
Enclosure 4.16 oP/i/All 105/014 OP!l/A/I1051014 Channel Check Of OTSG Downcomer Page 2 of3 of 3 Temperatures NOTE: Interpolation of the chart may be necessary for different power levels and OTSG outlet pressures.
3.2 Determine saturation temperature for 1lBB OTSG based on power level and 1lB B OTSG outlet pressure as follows:
JCi~Q M" 3.2.1 Determine IBlB OTSG outlet pressure using anyone any one of the following computer points:
- 01E2282
- OlE2284 01E2284 s*s;')
~ 3.2.2 322
.. lB OTSG saturation temperature Using table in Section 4, determine the IB based on power level and IBlB OTSG Outlet Pressure obtained in step 3.2.1.
lB OTSG saturation temperature IB
~~", 3 scl.L 23 3.2.3 O1E2012 SG Lower Downcomer Temperature Loop B to the IB Compare 01E2012 lB OTSG saturation temperature determined in step 3.2.2:
~11t I 1 3.2.4 IF 01E2012 SG Lower Downcomer Temperature Loop B is NOT within
+/- 4.9 of
°F of the IB lB OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable.
~'j.s~
-I ci oTf 3.2.5 O1E20l3 SG Lower Downcomer Temperature Loop B to the IB Compare OlE2013 lB OTSG saturation temperature determined in step 3.2.2:
3.2.6 01E2013 SG Lower Downcomer Temperature Loop B is NOT within IF OlE2013
+/- 4.9 of
°F of the 1IB B OTSG saturation temperature, then enter Condition A of SLC 16.7.5 for OTSG overfill protection system inoperable.
Enclosure 4.16 Enclosure 4.16 oP/i/All 105/014 OP/IIAlI105/014 Channel Check Channel Check OfOf OTSG OTSG Downcomer Downcomer Page Page 33 of3 of 3 Temperatures Temperatures
- 4. OTSG
- 4. Lower Downcomer OTSG Lower Saturation Temperature Downcomer Saturation Temperature eF) (°F) As As AA Function Function Of Of Power Level And OTSG Power Outlet Pressure OTSG Outlet Pressure NOTE:
NOTE: Interpolation of Interpolation of the chart may the chart may be necessary for be necessary for different different power power levels levels and and OTSG OTSG outlet outlet pressures.
Power OTSG Outlet Pressure (psig)
OTSG (psig)
Level i
(%) 860 860 870 870 880 880 890 890 900 910 920 15 529.1 529.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
Admin-303 fnl Page Page 11 of 7 REGION II INITIAL LICENSE EXAMINATION EXAMINATION PERFORMANCE MEASURE JOB PERFORMANCE 6r2o O!JC~
ADMIN-303 CALCULATION STAY TIME CALCULATION CANDIDATE EXAMINER
Admin-303 fnl Page 2 of 7 REGION II EXAMINATION LICENSE EXAMINATION INITIAL LICENSE PERFORMANCE MEASURE JOB PERFORMANCE MEASURE Task:
Determine stay time for an activity Alternate Path:
No Facility JPM #:
Admin 303 KIA Rating(s):
System: GEN K/A:
KIA: 2.3.7 Rating: 3.5/3.6 Task Standard:
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 (18.0-19.0 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
========================================================================
ENTS COMMENTS COMM
Mmlri-303 Admin-303 fnl fnl Page 3 ofT of 7 SIMULATOR OPERATOR INSTRUCTIONS:
None
Admin-303 fnl Admin-303 fnl Page4of7 Page 4 of 7 ToolslEguipment/Procedures Needed:
Tools/Equipment/Procedures Needed:
Radiation Work Radiation Work Permit Permit ##23 23 Survey Map Survey Map READ TO READ TO OPERATOR DIRECTION TO TRAINEE:
DIRECTION II 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. II 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 II provided you.
INITIAL CONDITIONS:
Unit 11 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,line, RWP 23, and Room 61 survey map provided:
- 1. State the amount
- 1. amount of dose that was received for the duration duration of this task.
- 2. Assuming you entered the room and began venting at the previously stated times, determine determine the maximum maximum time that you could vent the pump that you pump without exceeding aa limit limit imposed by the imposed by the RWP.RWP,
Admin-303 Admin-303 fnl fiil Page 5 of 7 Page5of7 START TIME: _ __
STARTTIME:
STEP 1:
STEP What dose 1: What will be dose will be received received for the duration for the duration ofof this this task?
task? CRITICAL CRITICAL STEP STEP Based on Based 30 minute on aa 30 minute wait wait at at the the LEWA LEWA and and 12 12 minutes minutes at at LPI LPI Pump Pump and and the the SAT SAT nearest posted general nearest posted general area area dose rates (12 dose rates (12 mr/hr):
mr!hr):
LEWA dose:
LEWAdose: 33 mr/hr mr/hr X X 0.50.5 hr hr == 1.5 1.5 mR mR UNSAT UN SAT Vent time Vent time dose dose Area dose is Area is 12160 hr 12/60 hr X 76 mr/hr mr/hr = 15.2 15.2 mR mR Estimated total Estimated total dose dose received received is 15.2=
1.5 ++ 15.2=
is 1.5 16.7 mR 16.7 mR NOTE: Acceptable range is 16.5 mR mRto 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 CRITICAL STEP before reaching a limit imposed by the RWP?
SAT Based on the nearest general area dose rates (76 mr/hr):
The RWP Dose Alarm is 25 mR.
UNSAT UN SAT LEWAis LEWA is 3mr/hrXO.5h 3 mr/hr X 0.5 hr r1.5mR = 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 mrmr == 0.309 hours0.00358 days <br />0.0858 hours <br />5.109127e-4 weeks <br />1.175745e-4 months <br /> or 18.5 18.5 minutes 76 mrlhr mr/hr Note:
Note: Acceptable range is 18.0 19.0 minutes.
18.0 - 19.0 STANDARD:
STANDARD: Calculates maximum maximum ventingventing time.
time.
COMMENTS:
COMMENTS:
END TASK END TASK STOP STOP TIME:
TIME: _ _ _ __
Admin-303 fnl Page 6 of 7 CRITICAL STEP EXPLANATIONS:
STEP # Explanation 1
1 Required to calculate dose received while performing task.
2 Required to calculate the maximum venting time.
CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
II 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. II 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 II provided you.
INITIAL CONDITIONS:
Unit 1 I is in AP/26, AP!26, Loss of Decay Heat Removal and you are to:
- Stage yourself inside Room 61 where you can minimize your dose while waiting
- IA LPI pump when directed Vent 1A 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 Date/Time 03/26/2010 13:06 DatelTime I Significant Dose Contributor
- 50 LEWA +30 d
~
20-371 0
I ENTIRE ROOM CONTAMINATED ~
ILPIIVOO94 HS#316 HS*100
+2J Comments: PLANVIEW UPDATED TO SHOW ENTIRE ROOM Summary of Highest Readings CONTAMINATED FOR RECOATING PROJECT. ALL DOSE RATE INFO. FROM PREVIOUS SURVEY M-020706-2 Smears Air Samples & Wipes 1)2554
- 1) 3/y 2554 DPM/100 cm2 [3Iy Symbol Legend (for example only) Type: Job Coverage Dose Rate Dose Rate IHS¥50 I Hot Hot Spot Spot RWP: 5036 till=
150 Contact Reading __
- 75
+75 30cm 30 em Reading ~ Posting Reactor Power =
= 100%
20 General Area Contact ~
J Drip Bog DripBag lil Smear M\ Air Sample ~ Wipe Unless otherwise noted, dose rates in mrem/hr.
SUrveyor: W. Walters Surveyor: Approved by: N. Wriston, 03/27/2010
Training Use Only Oconee Nuclear Station Training Use Only Radiation Work Permit Entry For Entry For Routine Routine Plant Plant And Systems OperationOperation RWP#23 RWP#23 . Rev:
Rev: 27 Task#1 Task #1 Entry for Routine Plant and S Ent Systems Operation in High Radiation Areas (Operations)
ED Alarm Set Points:
Dose Alarm: 10 Dose Rate Alarm: 50 Stay Time Alarm: 55:00 RWP Requirements CategorylWork Description Dress Category/Work
- Dress Category "A" A Work in a non-contaminated area
- Dress Category "B" B Work in a non-contaminated area with contaminated material where there is NO potential for contact with
- Dress Category "C" C Work in a non-contaminated area with contaminated material where there is NO potential for contact with
- Dress Category "D" D Work of short duration, in open area(s) with NO obstructions that could contribute to contamination of unprotected
- Dress Category "E" E Work where: (1) Complete protection of skin and clothing is NOT required; (2) Durability of surgical gloves requires
- Dress Category "F" F Work in a contaminated area where complete protection of skin and clothing is NOT necessary.
- Dress Category "G" G Work in a dry contaminated area.
- Dress Category "H" H Work in a contaminated area.
- Dress Category "I" I Hands on work with higher contaminated material or beta dose concerns to hands only.
- Dress Category "N" 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 Dosimetry Requirements
- 1.
- 1. High High noise level in the work area.
level in
- 2.
- 2. Use Use of head phones of head
- 3. 3. Hearing Hearing impairment impairment
- 4. 4. Any Any other condition condition that would impair impair hearing an ED ED alarm
- An Auxiliary Auxiliary ED alarm is required in areas where general rates are> 100 area dose rates 100 mrem/hr mrem/hr ifif any any of of the following conditions exist:
- Monitor ED periodically while inside the RCNRCZ (once or twice per per hour in low dose rate areas). Monitor more more frequently in higher higher dose Respiratory Protection
- IfIf weighted DAC-Hours are expected to result in greater than or equal to 44 DAC-Hours per person, perform aa TEDE/ALARA evaluation Approved Approved on on 11/12/2009 11/12/2009 by by ROBINSON, ROBINSON, LAGRONE LAGRONE D D Printed on Printed on 02/10/2010 02/10/2010 Activated Activated on 11/1212009 on 11/1212009
- Full Full Face Face Particulate Particulate (Additional (Additional Hood Hood Required)
Required) IF IF warranted warranted by by TEDE TEDE ALARA ALARA Evaluation Evaluation OR OR directed directed by by RP RP RP Hold RP Hold Points Points
- Accumulated Accumulated dose higher than dose higher than expected expected
- Notify Notify RP RP Prior Prior to to Start Start of of Work Work
- RP RP survey survey required required prior prior to to handling handling debris debris or or foreign foreign material material
- RP RP survey required required prior prior to handling handling valve/pump parts parts or or intemals internals Stop Work Criteria Stop Criteria
- Actual contamination contamination levels levels are are higher higher than the expected levels levels written on this RWP RWP task
- Dose Dose Alarm Alarm Failure of OR
- Failure OR sweat soaked protective protective clothing clothing
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 mrem/hr-- 100 mrem/hr General area dose rates: 0.1 mrem/hr High contact dose rates: 0.1 mrem/hr - 3000 mrem/hr dpm/lOOcm2 - 100,000 dpm/100cm2 (Beta/Gamma)
Contamination levels: <1000 dpm/100cm2 -
dpm/lOOcm2 --300 Contamination levels: 0 dpm/100cm2 dpm/lOOcm2 (Alpha) 300 dpm/100cm2 Additional Instructions Approved Approved on on 11/12/2009 11/12/2009 by by ROBINSON, ROBINSON, LAGRONE LAGRONE D 0 Printed Printed onon 02/10/2010 02/10/2010 Activated on Activated on 11/12/2009 11/12/2009
Training Use Only Oconee Nuclear Station Training Use Use Only Radiation Work Permit Entry For For Routine Plant And Systems Operation RWP#23 RWP#23 Rev:
Rev: 27 Task#2 Task #2 Entry for Routine Plant and S Entr Systems Operation in High Radiation Areas (Operations)
ED Alarm Set Points:
Dose Alarm: 25 Dose Rate Alarm: 500 Stay Time Alarm: 55:00 High Radiation Area Entry RWP ReqUirements Requirements Dress Category/Work Description
- Dress Category "A" A Work in a non-contaminated area
- Dress Category "B" B Work in a non-contaminated area with contaminated material where there is NO potential for contact with
- Dress Category "C" C Work in a non-contaminated area with contaminated material where there is NO potential for contact with
- Dress Category "0" D Work of short duration, in open area(s) with NO obstructions that could contribute to contamination of unprotected
- Dress Category "E" 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.
"F"
- Dress Category 0 Work in a dry contaminated area.
"G"
- Dress Category H Work in a contaminated area.
"H"
- Dress Category "I" I Hands on work with higher contaminated material or beta dose concemsconcerns to hands only.
- Dress Category "N" N Performing work in contaminated wet conditions.
- Modesty garments, top & bottom, are required under protective clothing where personal outer clothing is not worn wom Contamination Control
- Change outer rubber gloves often when handling highly contaminated material as directed by RP
- If installing aa drain rig, secure hose OR tubing to floor drain
- If installing aa 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 aa contaminated area as directed by RP RP Job Coverage
- Pre-job briefing required
- Start of Job, Job, Intermittent or No Coverage for work in High Radiation Areas or less
- 1.
- 1. High High noise level in in the work area.
- 2. Use of head
- 2. head phones
- 3. 3. Hearing Hearing impairment
- 4. 4. Any other condition that would impair impair hearing an ED ED alarm
exist:
- Monitor Monitor ED peilodically periodically while inside the RCNRCZ RCAfRCZ (once or twice per per hour hour in in low low dose dose rate areas). Monitor more more frequently in in higher dose dose Approved Approved on on 11/12/2009 11/1212009 by by ROBINSON, ROBINSON, LAGRONE D 0 Printed Printed on on 02/10/2010 02110/2010 Activated Activated on 11/1212009 on 11/12/2009
Respiratory Protection Respiratory Protection
- IfIfweighted weighted DAC-Hours DAC-Hours are expected to are expected to result result inin greater than or greater than or equal equal toto 44 DAC-Hours DAC-Hours per per person, perform aa TEDE/ALARA person, perform TEDE/ALARA evaluation evaluation
- Full Full Face Face Particulate Particulate (Additional (Additional Hood Hood Required)
Required) IF IF warranted warranted by by TEDE TEDE ALARA ALARA Evaluation Evaluation OR OR directed directed by by RP RP Hold Points RP Hold RP Points
- Accumulated Accumulated dose higher than dose higher expected than expected
- Notify Notify RP RP Prior Prior toto Start Start ofof Work Work
- RP RP briefing briefing required required prior prior to to entering entering High Radiation Areas High Radiation Areas
- RP RP survey survey required required prior prior to to handling handling debris debris or or foreign foreign material material
- RP RP survey required prior survey required prior to to handling handling valve/pump valve/pump parts or internals parts or internals Stop Work Criteria Stop Work Criteria
- Actual Actual dose rates are dose rates higher than are higher than the the expected expected levels written on levels written on this this RWP RWP task task
- Dose Dose Alarm Alarm
- Failure Failure of of OR OR sweat soaked protective sweat soaked protective clothing clothing
- IfIf monitoring monitoring of of the the EDED indicates indicates that that the dose alarm the dose alarm set point will set point will be be exceeded exceeded prior prior to to completing completing the the job, job, leave leave the area area and and contact contact RP.
RP.
Do not Do not wait wait to to receive receive an an alarm alarm before before exiting exiting the the area area
- Unexpected Unexpected dose dose rate rate alarm alarm
- Unexpected Unexpected wet wet conditions conditions
- Work Work scope changes scope changes Expected Radiological Conditions General area dose rates: 100 mrem/hr --700 700 mrem/hr High contact dose rates: 0.1 mrem/hr - 3000 mrem/hr -
Contamination levels: <1000 dpm/100cm2 Contamination dpm/lOOcm2 - 100,000 dpm/100cm2
- dpm/lOOcm2 (Beta/Gamma)
(Beta/Gamma)
Contamination levels: 0 dpm/100cm2 - 300 dpm/1 Contamination - dpmIlOOcm2 00cm2 (Alpha)
Additional Instructions Approved Approved on on 11/12/2009 11/12/2009by by ROBINSON, ROBINSON, LAGRONELAGRONE D0 Printed Printed on 02110/2010 on 02/10/2010 Activated on Activated on 11/12/2009 11/12/2009
Admin-402 fnl Page 11 of 17 Page 17 REGION II EXAMINATION INITIAL LICENSE EXAMINATION PERFORMANCE MEASURE JOB PERFORMANCE Admin-402 Perform Actions for Medical Emergency 7(Z OiUL-/
CANDIDATE EXAMINER
Admin-402 fnl Page 2 of 17 17 REGION II INITIAL LICENSE EXAMINATION MEASURE JOB PERFORMANCE MEASURE Task:
Perform Actions for Medical Emergency Alternate Path:
No Facility JPM #:
Admin 402 KIA Rating(s):
System: GEN K/A:
KIA: 2.4.39 Rating: 3.9/3.8 Task Standard:
RP/1000/016, Enc!.
Complete RP/1000I016, End. 4.1 (Medical Response).
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant _ _ Perform X Simulate
References:
000/01 6, Enc!.
RP/1 0001016, End. 4.1 (Medical Response)
Validation Time: 15 minutes Time Critical: NO
==========================================================================
Candidate: Time Start: _______
NAME Time Finish: _ __
Performance Rating: SAT ____ UNSAT _ __ Performance Time: - - -
Examiner: __________________________
~/-------/
NAME SIGNATURE DATE
==========================================================================
COMM ENTS COMMENTS
Admin-402 fnl Page 3 of 17 Page 17 INSTRUCTIONS:
SIMULATOR OPERATOR INSTRUCTIONS:
1.
- 1. Ensure ALL cables Ensure cables leading leading to MERT MERT activation phone phone are are disconnected.
- 2. RPIOIBI1000IO16 Verify RP/0/S/1 available in 000/016 clean copy available in control room RO RO bookshelf.
bookshelf.
- 3. Ensure radios are available and operable.
Ensure
Admin-402 fnl Page 4 of 17 Tools/Equipment/Procedures Needed:
RP/1000/016, RP/1 End. 4.1 (Medical Emergency Action - Routine Operations) 0001016, Enc!.
READ TO OPERATOR DIRECTION TO TRAINEE:
II 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. II 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 II 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.
Admin-402 fnl fnl Page 5 of 17 17 START TIME: _ __
1:
STEP 1: Determine the appropriate procedure to use.
Determine
- SAT STANDARD: RP!O!B/1000!016 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 UNSAT notebook located in the front of the control room desk or from the cart in -
the TSC.
COMMENTS:
STEP2:
STEP 2: Step 1.1 Complete the procedure steps that apply to this medical emergency, N/A - SAT steps not performed.
STANDARD: Complete Enclosure 4.1 as indicated on the Key.
- UNSAT COMMENTS:
Admin-402 Admin-402 fnl fnl Page Page 66 of of 17 17 STEP 3:
STEP 3: Step 1.2 Step 1.2 CRITICAL CRITICAL STEP STEP Complete the Complete the following following accident accident information:
information:
SAT SAT
- Name of Name of person person reporting reporting injury injury -
- Call back number Call back number
- Name of Name of person person injured injured UNSAT UNSAT
- Supervisor of Supervisor of injured injured person person -
- Location injury Location injury occurred
- Brief Brief description of injury injury
- Date/Time Date / Time provide a copy of the attached information Cue: The evaluator should provide 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 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 - - SAT ONO3EP ON03EP STANDARD: Determine MERT MERT is still required and continue. UNSAT COMMENTS:
Admin-402 fnl Page 7 of 17 17 STEP 5: Step 1.4 Step 1 .4 IF There is IF Event in progress, is a Security Event progress,
- SAT THEN Continue with with...
STANDARD: Determine a Security Event is not in progress and N/A step 1.4.
- UNSAT UN SAT in form candidate a Security Event is not in progress.
Cue: If asked, inform COMMENTS:
STEP6:
STEP 6: Step 1.5 IF MERT activation is required THEN perform the following: - SAT
- Use Plant Page to request all MERT members to respond to the incident.
- UNSAT
- 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 ff1 Page 8 of 17 17 STEP 7: Step 1.5.11.5.1 CRITICAL STEP Use the following directions to activate radios Use radios and pagers encoded to the MERT alert tones: SAT
- 1. Press the "GREEN" MERT on the paging console GREEN button labeled "MERT"
- 2. RED Button labeled "transmit" Press the "RED" transmit on the right bottom of the UNSAT console and wait approximately 3 seconds.
- 3. handset on console and press the lever located Pick up telephone "handset" 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 Operations contains the word "Operations" GREEN button labeled "MERT" Press the "GREEN" 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" RED Button labeled "transmit" 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" "warble tone is heard when the TRANSMIT button is depressed.
handset on console and press the lever located Pick up telephone "handset" inside the handset Transmit message COMMENTS:
PT <t -l-ks sk s Gr&tded ct.£,.
a SIiJ1l.s.p~~. jS sFO-Thf kS W(\~ &s: ~ a.f~'lcan ~
- 1) eA"06.g.,e J ~ &~t-l -&.; ~
+R-e 4 ~{'e<!;&--J re 'iV&'O (/
\-te jO 8 Bu ~(\ ~ 4 US~ ~
'ra.V\~ ~-ee) 1 ~('AS'6e/d ~ {-ever (r ~ Tro. TrtsfV1Si11 dIve!
J!l-
~e /Yl";5~.
Admin-402 Admin-402 fnl fnl Page Page 99 of of 17 17 STEP 8:
STEP 8: Step 1.5.2 Step 1 .5.2 IF Paging IF Paging system system is is inoperable inoperable in in Unit Unit 11 Control Control Room, Room, - SAT SAT THEN Request THEN Request UnitUnit 33 Control Control Room Room toto activate activate MERT MERT oror use use paging paging system located system located in in TSC.
TSC.
UNSAT U N SAT STANDARD:
STANDARD: Determine paging Determine system is paging system operable and is operable and N/A N/A the the step.
step.
Cue: If Cue: If ask, ask, inform in form candidate candidate that that paging system system is operable.
COMMENTS:
STEP 9: Step 1.5.3 1 .5.3 Repeat Steps 1.5 and 1.5.1. - SAT STANDARD: Repeat steps 1.5 and 1.5.1.
- UNSAT U N SAT COMMENTS:
INOTE: Do NOT call Securit~
!NOTE: Security if there is a securit~
security event in Qrogress.1 progress.
10:
STEP 10: Step 1.5.4 1.5.4 - SAT 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 UNSAT
- UNSAT
. CAS (Central Alarm Station) 2222 or 2958 STANDARD:
STANDARD: Security isis notified atat one one of of the above extensions and and are are requested to have have security MERT MERT members members respond to the the emergency.
COMMENTS:
Admin-402 Admin-402 fnl fnl Page Page 10 10 of of 17 17 NOTE: IF NOTE: IF the the MERT MERT incident incident occurs occurs away away from from the the main main plant plant (World (World of of Energy, Energy, Keowee Hydro, Keowee Hydro, Complex, Complex, etc.)
etc.)
THEN aa shuttle THEN shuttle bus bus will be be required required to to transport transport responding responding MERT MERT personnel.
personnel.
- SAT STEP11:
STEP 11: Stepl.5.5 Step 1.5.5 IF The incident occurs during normal working hours and shuttle bus service is required. UNSAT THEN Call extension 5353 and 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: - SAT STANDARD: Determine that this step does not apply and N/A step 1.6
- UNSAT UN SAT 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,
- SAT THEN Make aa PA Announcement...
Announcement ...
STANDARD: Determine that this step does not apply and N/A step 11.7 .7 UNSAT UN SAT COMMENTS:
Admin-402 Admin-402 fnl fnl Page Page 11 11 of of 17 17 STEP 14:
STEP 14: Step 1.8 Step 1.8 CRITICAL CRITICAL STEP STEP IF Hospital IF Hospital evacuation evacuation is is needed needed as as determined determined by by MERT MERT Command Command or or as indicated as indicated byby Step Step 1.8.1, 1.8.1, THEN Arrange transport of patient to the hospital by one of the following SAT means:
- EMS (ambulance) 9-91 1 from the Operations Shift Manager's Dial 9-911 Managers phone or Unit 11 UNSAT Control Room SRO'sSROs phone or dial 911 from the bell South line -
1, 2, and 3 Control Rooms. Refer to Step 1.8.2, Unit 1, 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. 9-91 1. Ambulance is requested to come to Oconee Nuclear Station.
COMMENTS:
n Cc1L 14)T f 40 GLJT pi uac/1 ( ) C AcLJd.
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: SAT
- Unconsciousness UNSAT STANDARD: Determine that the injured is unconscious and perform step 1.8. 1.8. (Step 14 14 above)
Cue: This will have to be simulated only since simulator phones do not model outside lines.
COMMENTS:
COMMENTS:
Admin-402 fnl Page Page 12 12 of 17 17 STEP 16:
STEP 16: Step 1.8.2 Step 1.8.2 IF The patient IF patient is is known known or suspected to be radiologically contaminated, be radiologically contaminated, THEN Request THEN Request from from MERT MERT...... SAT STANDARD: Determine that this step does not apply and N/A step 1.8.2 1 .8.2 if asked, inform candidate that the patient is NOT contaminated.
Cue: If UNSAT 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 - SAT COMMENTS:
- UNSAT U N SAT STEP 18: Step 1.8.4 CRITICAL STEP Notify MERT Command that the ambulance is enroute.
STANDARD: MERT Command is notified via radio that the ambulance is enroute.
- SAT COMMENTS:
- UNSAT U N SAT STEP 19: Step 1.8.5 1.8.5 Notify World of Energy/Public Affairs Duty Person (Ext. 4602 during operating hours).
- SAT STANDARD: World of Energy Duty Person is notified by phone.
COMMENTS: UNSAT
Admin-402 fnl Page 13 of 17 STEP 20: Step 1.9 1 .9 IF Radiological contamination is involved and the person is being sent to a hospital.
THEN Complete ...
Complete... - SAT STANDARD: Determine that this step does not apply and N/A step 1.9. 1 .9.
- UNSAT UN SAT 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 - SAT Medical Unit for inclusion in the patient's patients medical file.
STANDARD: MERT Command is informed that a Patient Treatment Form needs to be completed and sent to the Medical Unit. - UNSAT In form candidate to simulate only_
Cue: Inform only.
COMMENTS:
STEP 22: Step 1.11 IF after normal working hours ...
hours...
STANDARD: Determine that this step does not apply and N/A step 1.11. - SAT COMMENTS:
- UNSAT
Admin-402 fnl Page 14 14 of 17 17 STEP 23: Step 1.12 1.12 In the event of a fatality In fatality...
STANDARD: Determine that this step does not apply and N/A step 1.12.
Determine SAT COMMENTS:
UNSAT UN SAT 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.
- SAT STANDARD: STA Notify the ST A to make appropriate notifications of the transport.
- UNSAT COMMENTS:
STEP25:
STEP 25: Step 1.14 IF A death, near death, or major traumatic injury incident occurs ...
occurs...
- SAT STANDARD: Determine that this step does not apply and N/A step 1.14.
COMM ENTS:
COMMENTS: UNSAT STEP 26: Submit completed Enclosure 4.1, (Medical Emergency Action Routine
-Routine Operations) to the Emergency Planning Section.
STANDARD: Indicate that the completed form would be submitted to the Emergency SAT Planning Section.
Cue: Another operator will continue with this procedure and the JPM is completed.
- UNSAT COMMENTS:
END TASK STOP TIME: _ _ _ __
Admin-402 fnl Page 15 15 of 17 17 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 rd 3
( rd The injured is currently located in the clean side of Unit 3's 3s change room (3 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
Admin-402 fnl Admin-402 fnl Page 16 Page 16 of of 17 17 CRITICAL STEP EXPLANATIONS:
STEP # Explanation 3 Needed to complete the procedure.
7 Need to activate MERT.
14 Ambulance has to be requested.
18 MERT command should be notified so that the injured can be taken to the pickup point.
Admin-402 Admin-402 fnl fnl Page Page 17 of 17 17 of 17 CANDIDATE CUE CANDIDATE CUE SHEET SHEET (TO BE (TO BE RETURNED RETURNED TO TO EXAMINER EXAMINER UPON UPON COMPLETION COMPLETION OFOF TASK)
TASK)
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 perform the required actions for a medical emergency.
Enclosure 4.1 j.P/OiB/l 9O/O 16 Medical Emergency Actions Routine Operations
- 1. Medical Emergency Actions Routine Operations NOTE:
- Security Manager or designee in the Operational Support Center (OSC) will assume 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.
1.1 Complete the procedure steps that apply to this medical emergency, NI N/A A steps not performed.
/1.2 Complete the following accident information:
Name of person reporting injury ~
Jp0 h n 1 iA dclc.w.-. SQ.VV'\
Call back number --=~~3....c-<.2~:>::~,-,--
2.. ______________
Name ofperson(s) of person(s) injured:
D;d Supervisor of injured person: ----'--A-F-'L1o.
-'-ll-'-'Q..::.../}--<---_""-'>\.....,D'-"--'-O--'--"'L:=>-.Sl---_ _ _ _ _ _ __
Location injury occurred U,- Ul"\i=1 '3 3 1-) P.l:
ti P1 -:p, \ P ty\ p Ko c,pv OVVl Brief description of injury -+ h h ;.;. \-. e.4 A0 c C) c..1A.6\ ep TIC!. 2:) ce..$v lH~
1 IQ..C.lLr~trU/l 10 lr To p top p of h%-d.
o Q(J. WOI.ln.J. flL1 CoQ+/-Jl)v~\ ro bl.aeJ.
'P e.r So 1'\ 1i-SS U,.,
?ar-sf- Co\) r"\ S C, 0 \.J S O$Cjoj3 iA S DCA+e.
Date Tod"u Time c.urre..,.+ ( JrfO,-, + 1 I'-~..e....
I
Enclosure 4.1
/O,B/1ooo/o16 RP 10fBI 100010 16 Medical Emergency Actions Page 2 of9 of 9 Routine Operations 1.3 1.3 IAAT IAAT MERT response is is NO longer longer required.
THEN Exit this procedure and forward to Emergency Planning - ON03EP
- ONO3EP {6}
{6}
NOTE: Do NOT activate MERT when a security event is in progress until Security confirms that MERT it is safe for MER T members to respond.
cç). I A.i . IF There is a Security Event in progress, THEN 1.4.1 or 1.4.2 Continue with Step 1.4.1 1.4.2 as appropriate; if NOT, go to Step 1.5.
1.5.
1.4.1 IF The patient is outside the Protected Area, THEN Dial 9-911 Managers phone or Unit 11 9-91 1 from the Operations Shift Manager's Control Room SRO'sSROs phone or dial 911 from the Bell South line:
1/2 and 3 Control Rooms. Request EMS to respond along with Units 112 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 1.5..
. . / 1.5 IF MERT activation is required THEN perform the following:
V V 1. Use Plant Page to request all MERT members to respond to the incident.
V V 2. Use the radio paging system to request MERTMERT 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. GREEN button labeled "MERT" Press the "GREEN" MERT on the paging console
- 2. Press the "RED" transmit on the right bottom of the RED Button labeled "transmit" console and wait approximately 33 seconds.
- 3. Pick up telephone handset "handset" on console and press the lever located inside the handset
- 4. Transmit message
Enclosure 4.1 Enclosure 4.1 IO/BI1ooo!o RP/O/B/1 000/016 16 Medical Emergency Medical Emergency Actions Actions Page Page 33 of9 of 9 Routine Operations Routine Operations WI 11 1.5.2
~ 1.5.2 IF Paging system isis inoperable Paging system inoperable inin Unit Unit 11 Control Control Room, Room, THEN Request THEN Request Unit Unit 33 Control Control Room Room toto activate activate MERT MERT or or use use paging paging system system located in located in TSC.
TSC.
/1.5.3
/1.5.3 Repeat Steps Repeat Steps 1.51.5 and 1.5.1.
and 1.5.1.
NOTE:
NOTE: Do NOT Do NOT call call Security Security if if there there is security event is aa security event in in progress.
V 1.5.4 1.5.4 Call Security Call Security atat one one of thethe following following extensions and request they have SecuritySecurity MERT members respond to the emergency.
SAS (Secondary SAS (Secondary Alarm Station) Station) -- 2205 or 2205 or 2767 2767 CAS (Central Alarm Station)-Station) - 2222 or 2958 NOTE: !J.
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 MER MERT T personnel.
c)(I// A- 1.5.5 IF The incident occurs during normal working hours and shuttle bus service is required.
THEN Call extension 5353 and
- Request shuttle bus to meet MERT MERT responders at main entrance of protected area for for transport to emergency scene.
- Make PA/Radio PA/Radio announceme announcement nt that a bus has been requested to meet MERT MERT responders at main entrance of protected area for transport to emergency emergency scene. {3 }
{3}
4.1 Enclosure 4.1 Enclosure 10fBI 10001016 1p/O,B/1oooIol6 RP Medical Emergency Medical Emergency Actions Actions Page Page 44 of9 of 9 Routine Operations Routine Operations 0vIA 1.6 16 IF IF incident involves The incident The involves aa trench trench collapse collapse THEN THEN Contact Oconee Contact Oconee Rural Rural Fire Fire by one of by one the following of the following methods:
methods:
- Dial 9-911 from Ext. 3271 from 3271 Operations Shift Manager's Managers phone
- Dial 911 Dia1911 from 882-7076 882-7076 1, 2, &
Units 1, & 3 Control Room, Bell South lines A. Request a response from:
oLI Keowee Fire Department oLI Keowee Ebenezer Fire Department oLI 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.
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.
~1.7 e
1 j A 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 PA Announcement emphasizing the following:
- Location of the Triage area
- Warn that only Warn only trained medical medical personnel personnel should should move move injured injured people people unless there are life threatening conditions conditions in the area.
Enclosure 4.14.1 10IBII 00010 16 RP/O/B/l000lol6 RP Medical Emergency Actions Medical Page 55 of9 of 9 Operations Routine Operations NOTE:
- Occupational Health Unit may call direct and request an ambulance without going 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.
V 1.8 determined by MERT Command or as Hospital evaluation is needed as detennined indicated by Step 1.8.1, THEN Arrange transport of patient to the hospital by one of the following means:
- EMS (ambulance)
- Managers phone or Unit 11 Control Dial 9-911 from the Operations Shift Manager's SROs phone or dial 911 from the Bell South line - Units 112 Room SRO's - 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)
V 1.8.1 jj 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 deformity defonnity or open wounds)
- amputations
- allergic reaction WITH airway compromise (swollen lips, tongue)
- poisonous snake bite
- head injury with altered level of consciousness (conflision, (confusion, disorientation)
- altered mental status (confusion, disorientation)
- seizure (grand (grand mal)
- respiratory distress
- entrapped person
- crushing injuries injuries THEN Immediately request EMS (ambulance)
THEN (ambulance) to respond to the site.
site.
Enclosure 4.1 10fBI 100010 16 RP/O/B/l000/016 RP Medical Emergency Actions of 9 Page 6 of9 Routine Operations 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
.8.2 IF The patient is known or suspected to be radiologically contaminated, THEN Request from MERT command the extent of contamination (gross contamination, PC contamination, modesty garment) and if possible contamination levels.
9-882-46 1 1 with the above Call Oconee Memorial Hospital, 9-882-4611 information.
/V 1.8.3 Noti Security at 2222 that the ambulance is enroute.
Notify V" 1.8.4 Notify MERT Command that the ambulance is enroute.
/ 1.8.5 Energy/Public Affairs Duty Person (Ext. 4602 during Notify World of EnergylPublic operating hours).
NOTE: IF Transportation of a radiologically contaminated person to an offsite medical facility is required.
THEN The NRC must be notified within eight (8) hours (ref. 10CFR50.72 10CFR5O.72 (b) (3)
(xii).
~/A1.91.9 IF 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 RP/Om/1 RP /0 IBII 000/0 000/016 16 Medical Emergency Actions of 9 Page 7 of9 Routine Operations
~)l-1.9.3 1.9.3 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 TreatmentlTransport Against Medical Advice Form needs to be completed for all patients Treatment/Transport 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.
~
~1.11 1.11 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 33 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
- burns Electric contact, shock or flash bums
- Injuries or burns 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.
Enclosure 4.1 RP /0 IBIl 000/0 RP/O/B/1 000/016 16 Medical Emergency Actions of 9 Page 88 of9 Routine Operations JJ
~1.12 I) In the event of a fatality (including all fatal heart attacks at work) or admission of 33 or more employees to the hospital for in-patient care, ensure the OSM or designee performs the following.
1.12.1 Notify EH&S Duty person who will notify OSHA (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> oral reporting requirement).
1.12.2 Refer to NSD 202 for other reportability requirements.
1.12.3 Notify Site VP or his designee.
Vl.13 IF 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.
~4 IF A death, near death, or major traumatic injury incident occurs, {1}
{I}
L THEN Notify Employee Assistance Program at extension 3315 or 9-704-382-7900.
~ 1.14.1 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
- MERT 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 /0 IBIl 00010 16 RP/O/B/l000/o16 RP Medical Emergency Actions 9 of 9 Page 90f9 Routine Operations 1.18 employees supervisor to notify the OSM:
Inform the employee's {4}
- 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:
1.19.1 Document information on OSM turnover sheet and keep for 30 days.
A. IAA IAAT 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.
- Employees Supervisor or Manager perform Injury requiring hospitalization - Employee's
ADM-405 fnl Page 11 of 14 14 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-405 SOD OJuJ 5?O OAJ'vi Determine Emergency Classification and Protective Action Recommendations CANDIDATE EXAMINER
ADM-405 fnl Page 2 of 14 REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:
Determine Emergency Classification and Protective Action Recommendations Alternate Path:
NO Facility JPM #:
Admin-405 KIA Rating(s):
System: GEN KIA:
K/A: 2.4.41 Rating: 2.9/4.6 Task Standard:
Appropriate classification is determined and associated Emergency Notification Form is completed.
Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X In-Plant _-,-X-,-_
X Perform Simulate _X_X
References:
RP 10lBI 1000101 RP/0/B/1 000/0 1 RP/O/B/1000102 RP/0/B/1 00 0/02 BASIS Document (Volume "A", D of the Emergency Plan)
A, Section "0" mm.
Validation Time: 20 min. Time Critical: Yes
========================================================================
Candidate: Time Start: _ _ __
NAME Time Finish: - - - -
Performance Rating: SAT _ _ _ UNSAT _ __ Performance Time: - - - -
Examiner: _ _ _ _ _ _ _ _ _ _ _ ____ /
NAME SIGNATURE DATE
========================================================================
Comments
ADM-405 ADM-405 fnlfn Page 33 of Page of 14 14 SIMULATOR OPERATOR SIMULATOR OPERATOR INSTRUCTIONS:
INSTRUCTIONS:
ADM-405 fnl Page 4 of 14 14 Tools/Equipment/Procedures Needed:
RPIO/BI1000IO1 1/ RP/O/B/1000102 RP/O/B/1000101 RP/01B11000102 BASIS Document (Volume "A", A, Section "0" D
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. II 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 II provided you.
INITIAL CONDITIONS:
Unit 2 at 100% power 0900: Reactor trip due a Sheared RCP shaft on 2A 2A11 RCP 0900: Control Room has indications that the 2A 2A11 RCP Seals have failed 0904: ES 11 & 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/0/B/1 RP/O/B/1 000/01, Emergency Classification:
- 1. Determine Emergency Classification and record the time here. _ _ _ _ __
1.
- 2. Complete appropriate Emergency Notification Form for the current conditions.
THIS IS A TIME CRITICAL JPM Note: Do not use Emergency Coordinators Coordinator's judgment while classifying the event. When required, Jim Turner will maintain the Emergency Coordinators Coordinator's Log, assume the duties of the Control Room Offsite Communicator and activate the ERO pagers if desired.
ADM-405 ADM-405 fnlfnl Page Page 55 of of 14 14 START TIME: _ __
STARTTIME:
STEP 1:
STEP 1: Classify the Classify the Event Event at at 0915 0915 CRITICAL CRITICAL STEP STEP STANDARD:
STANDARD: Refer to Refer to RP/O/B/1000101 RP/0/B/1000/01 (Emergency (Emergency Classification)
Classification) Enclosure Enclosure 4.1 4.1 Matrix).
(Fission Product Barrier Matrix). -
SAT General Emergency" Classify the event as a "General Emergency due to the following:
Fission Product Barrier Matrix UNSAT
- 5 points for RCS Barriers due to 11 RIA-57 reading
- 5 points for Fuel Clad Barriers due to 11 RIA-57 reading
- 3 points for Containment Barriers due to (Rapid unexplained increase containment pressure decrease after increase" 13 points total results in a General Emergency
- *Determine
- Determine 4.1.G.2 4.1 .G.2 Loss of all 3 Barriers Time for Classification
- Note: Required to classify the event within 15 minutes of starting.
- Note:
RP/0!B/1000/002 (Control Room Emergency Coordinator GO TO RP/O/B/10001002 Procedure)
COMMENTS:
STEP2:
STEP 2: Step 1.1 occurred...
Events have occurred ...
- SAT STANDARD: Determine Emergency Plan has been activated and sign step.
- UNSAT UN SAT COMMENTS:
STEP 3: Step 2.1 IF No EAL exists...
exists ...
- SAT STANDARD: Determine Determine aa General Emergency Emergency does does exist and and N/A the step.
step.
- UNSAT U N SAT COMMENTS:
COMMENTS:
ADM-405 fnl Page 66 of of 14 STEP 4: Step 2.2 Declare the appropriate Emergency Classification the appropriate Classification level.
Classification (UE, Alert, SAE, GE)
(UE, GE) SAT SAT Time Declared:
- UNSAT UN SAT 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
- SAT STANDARD: Determine a security event is NOT in progress and N/A step.
COMMENTS: - UNSAT STEP 6: Step 2.4 IF assistance from ERO personnel is desired/required:
THEN activate ERO pagers from the ERO Pager Activation Panel:
- SAT
- For an EMERGENCY press "Test" Test button then press button 1 I
- For a DRILL press Test "Test" button then press button 3 3
- UNSAT U N SAT STANDARD: Determine that assistance is desired.
Note: The Control Room Offsite Communicator will activate the ERO pagers.
COMMENTS:
ADM-405 fnl Page Page 7 of 14 14 STEP 7:
STEP 7: Step 2.5 Step Control Room Appoint Control Offsite Communicator(s)
Room Offsite Communicator(s) and perform perform the - SAT following:
Record Name Record Name
- UNSAT UNSAT
- Offsite Communicator to REFER TO RP/O/B/10001015A, Notify Offsite RP/OIB/l 000/01 5A, 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.
recorded.
COMMENTS:
STEP 8: Step 2.6 IAAT Changing plant conditions require an emergency classification -
SAT upgrade, THEN Notify Offsite Communicator to complete the in-progress RP/0/B/1000/15A, notifications per RP/O/B/1 OOO/15A, (Off (Offsite site Communications From The
- UNSAT 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 ADM-405 fnlfnl Page Page 88 of of 14 14 STEP 9:
STEP 9: Step 2.7.1 Step 2.7.1 CRITICAL CRITICAL STEP STEP Obtain the Obtain the applicable applicable Offsite Offsite Notification Notification form form in in the the control control room room and and complete complete as as follows:
follows: SAT SAT
- UNSAT STANDARD: 4.1 .G.2 is selected.
EAL # 4.1.G.2 COMMENTS:
STEP 10: Step 2.7.2 Line 11 - Mark appropriate box "Drill"
- Drill or "Actual Actual Event" Event -
SAT STANDARD: Drill Mark "Drill" UNSAT UN SAT COMMENTS:
STEP 11: Step 2.7.3 CRITICAL STEP Line 11 - Enter Message #
- SAT STANDARD: Enter Message # 11 COMMENTS:
COMMENTS: -
UNSAT
ADM-405 fnl Page 9 of 14 STEP 12: Step 2.7.4 Step CRITICAL STEP Line 2 - Mark Line - Mark Initial Initial STAN DARD:
STANDARD: Mark Initial Mark Initial SAT COMMENTS:
- UNSAT UN SAT STEP 13: Step 2.7.5 Line 6 - A. Mark "Is
- Is Occurring" Occurring if any of the following are true: - SAT
- . RIAs 40, 45, or 46 are increasing or in alarm
- If containment is breached
- . Containment pressure> 1 1 psig - UNSAT None if none of the above is applicable.
Mark "None" STANDARD: Is Occurring" "Is Occurring is pre-marked on form.
COMMENTS:
STEP 14:
14: Step 2.7.6 Line 77 - If Line 66 Box B
- B or C C is marked, mark Box D. -
SAT Otherwise mark Box A STANDARD: "Under Evaluation Under Evaluation" is pre-marked on form.
- UNSAT U N SAT COMMENTS:
ADM-405 ADM-405 fnlfnl Page 10 of Page 10 of 14 14 STEP 15:
STEP 15: Step 2.7.7 Step 2.7.7 CRITICAL CRITICAL STEP STEP Line 8 Line 8 - Mark
- Mark "Stable" Stable unless unless an upgrade or an upgrade or additional additional PARs PARs are are anticipated within an anticipated within an hour. hour. SAT SAT
- . Refer to
. Refer Enclosure 4.9, to Enclosure 4.9, (Event (Event Prognosis Prognosis Definitions)
Definitions)
STANDARD:
STANDARD: Mark "Stable".
Mark Stable. UNSAT UNSAT COMMENTS:
COMMENTS:
STEP 16:
STEP 16: Step 2.7.8 Step 2.7.8 CRITICAL CRITICAL STEP STEP Line 10 - Military time and date of declaration (Refer to date/time in Step 2.2)
- SAT STANDARD:
STANDARD: Enter date and time entered in Step 2.2.
COMMENTS:
COMMENTS: UNSAT STEP 17: Step 2.7.9 Line 11 11 - Iff more than one unit affected, mark All "All"
- SAT SAT STANDARD STANDARD:: Mark Mark Unit Unit 2. 2.
COMMENT COMMENTS: S: UNSAT UNSAT
ADM-405 fnl ADM-405 fnl Page Page 11 11 of of 14 14 STEP 18:
STEP 18: 2.7.10 Step 2.7.10 Step Line 12 Line 12-- Mark Mark unit(s) unit(s) affected affected (reference (reference Line Line 11)
- 11) AND AND enter enter percent percent power for power for each each unit unit affected.
affected. SAT SAT
- IfIf affected affected unit unit is is shutdown, shutdown, then then enter enter shutdown shutdown time time and and date.
date.
STANDARD:
STANDARD: For Unit 22 Enter For Unit Enter 0900 0900 and and today's date.
todays date. - UNSAT UNSAT Note: Other Note: Other Unit's Units data data is is NOT NOT required required for for the initial notification.
the initial notification.
COMMENTS:
STEP 19: Step 2.7.11 Line 13 - If the OSM has no remarks, write "None"
- None
- SAT STANDARD: Enter None.
- UNSAT U N SAT COMMENTS:
STEP 20: Step 2.7.12 If Condition "A" A exists ensure following PAR's PARs are included on Line 5. - SAT
- Evacuate: Move residents living downstream of the Keowee Hydro Project dams to higher ground
- Other: Prohibit traffic flow across bridges identified on your - UNSAT inundation maps until the danger has passed.
STANDARD: Determine Determine Condition Condition A"A" does does NOT NOT exists andand N/A N/A step.
step.
COMMENTS:
COMMENTS:
ADM-405 ADM-405 fnl fn Page Page 12 12 of of 14 14 STEP 21:
STEP 21: 2.7.13 Step 2.7.13 Step CRITICAL CRITICAL STEP STEP Line 17 Line 17 - OSM
- OSM signature, signature, CURRENT CURRENT Time/Date Time/Date SAT SAT STANDARD:
STANDARD: Signs form Signs form and and enters enters CURRENT CURRENT Time/Date.
Time/Date.
Form complete Form complete within within 15 15 minutes minutes of of classification classification in in step step 2.2.
2.2.
UNSAT UNSAT COMMENTS:
COMMENTS:
END TASK TIME STOP: _ __
ADM-405 ADM-405 fnl fnl Page 13 of Page 13 of 14 14 CRITICAL STEP CRITICAL STEP EXPLANATIONS:
EXPLANATIONS:
STEP ##
STEP Explanation Explanation 11 Required to classify event as a General Emergency.
Required Emergency.
99 Ensures that the Ensures the correct correct communication communication form isis selected.
selected.
11 Required to accurately complete notification form.
12 12 Required to accurately complete notification form.
15 Required to accurately complete notification form.
16 Required to accurately complete notification form.
21 Required to complete communication form with 15 minutes of classification.
CANDIDATECUE CANDIDATE CUESHEET SHEET (TOBE (TO BERETURNED RETURNEDTO TOEXAMINER EXAMINERUPON UPONCOMPLETION COMPLETIONOF OFTASK)
TASK)
READ TO READ TO OPERATOR OPERATOR DIRECTIONS TO DIRECTIONS TO STUDENT:
STUDENT:
I I will will explain explain the the initial initial conditions, conditions, andand state state the the task task to to be be performed.
performed. AllAll control control room room steps shall be performed steps shall be performed for this JPM, forthis JPM, including including any any required required communications.
communications. II will will provide initiating provide initiating cues cues andand reports reports onon other other actions actions when when directed directed by by you.
you. Ensure Ensure you you indicate to me when indicate to me when you understandyou understand your your assigned assigned task.
task. To To indicate indicate that that you you have have completed your completed your assigned assigned task task return return the the handout handout sheet sheet II provided provided you.
you.
INITIAL CONDITIONS:
INITIAL CONDITIONS:
Unit 22 at Unit at 100%
100% power power 0900: Reactor 0900: Reactor triptrip due due aa Sheared Sheared RCP RCP shaft shaft onon 2A 2A11 RCP RCP 0900: Control 0900: Control RoomRoom has has indications indications that that the the 2A 2A11 RCP RCP Seals Seals have have failed failed 0904: ES 0904: ES 11 && 22 actuated actuated
- RB pressure =
RB pressure 4.7 psig and increasing
= 4.7 increasing
0915: RB RB Pressure Pressure == 0.2 psig and stable INITIATING INITIATING CUE:
You You are are to to perform perform the required actions of of the the Emergency Emergency Coordinator Coordinator by by referring referring to to RP/0/B/1 000/01, Emergency RP/O/B/1 000/01, Emergency Classification: Classificatio n:
1.
- 1. Determine Determine Emergency Emergency Classificatio Classification n and and record record the the time time here.
here. _ _ _ _ __
- 2. Complete
- 2. Complete appropriate appropriate Emergency Emergency Notification Notification FormForm for for the the current current conditions.
conditions.
THIS THIS IS IS AA TIME TIME CRITICAL CRITICAL JPM JPM Note:
Note: Do Do notnot use use Emerg Emergency ency Coordi nators judgm Coordinator's judgment while classif ent while classifying ying thethe event. When event. When require d, Jim required, Jim Turner Turner will will maintain maintain thethe Emerg Emergency ency Coordi Coordinator's Log, assume nators Log, assume the the duties duties of of thethe Control Control Room Room Offsite Offsite Comm unicator and Communicator and activat activate the ERO pagers if e the ERO pagers if desired.desired.