ML112800688
| ML112800688 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/04/2011 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-259/11-302, 50-260/11-302, 50-296/11-302 | |
| Download: ML112800688 (133) | |
Text
Admin RO Ala PAGE 1
OF 4
OPERATOR:
JPM NUMBER:
Admin RO Ala TASK NUMBER:
U-000-AD-17 TASK TITLE:
Determine Adequate Performance of License Reactivation KJA NUMBER: 2.1.4 KIA RATING: RO 3.3 TASK STANDARD: Determine which of the reactivating personnel have correctly completed the reactivation requirements.
LOCATION OF PERFORMANCE:
Class Room REFERENCES/PROCEDURES NEEDED: OPDP-l0 VALDATION TIME: 10 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS:
SATISFACTORY___
UNSATISFACTORY SIGNATURE:
DATE:
EXAMINER
INITIAL CONDITIONS:
3 off-shift licensed personnel are returning to shift from rotating assignments and are reactivating their licenses. The following table gives information as to hours worked under direction of an activated licensee, tours performed, etc.
Pre-activation License Meeting Shift 1 Shift 2 Shift 3 Shift 4 Shift 5 Shift 6 Plant Tour Ups Training 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs Per SM Manager U-3 RU U-3 RU U-i RU tagging U-2 RU U-2 RU instructions ROl Shift Manager UO RU conducted complete plant tour with STA (SRO)
Ups Training 12 hrs 12 hrs 12 hrs 12 hrs l2hrs Per SM Manager U-2 RU U-2 RU U-i RU U-3 RU U-3 RU instructions Ups Called conducted Superintendent for complete plant Random tour with extra R02 Drug test RU assigned to during that shift crew shift
missed end of shift turnover Ups Training 12 hrs 12 hrs 12 hrs 12 hrs 12 hrs Conducted Manager U-2 RU U-2 RU U-3 RO U-3 RU U-I RU complete plant R03 Ups tour with U-2 Superintendent RB AUO INITIATING CUE:
The Shift Manager has tasked you to determine which of the personnel, if any, have completed the requirements for license reactivation. If any personnel do not meet the requirements for license reactivation state the reason(s) why.
Admin RO Ala PAGE 3
OF 4
START TIME____
Performance Step 1:
Critical X Not Critical Analyzes information provided to determine which personnel meet the requirements for license reactivation.
Standard:
Determines RO 2 meets the requirements for license reactivation.
SAT UNSAT N/A COMMENTS:
Performance Step 2:
Critical X Not Critical States the reason why RO 1 does not meet the requirements for license reactivation.
Standard:
RO 1 did not interview with Ops Superintendent contrary to OPDP-10.
SAT UNSAT N/A COMMENTS:__________________________
Performance Step 3:
Critical Not Critical States the reason why R03 does not meet the requirements for license reactivation.
Standard:
R03 performed plant tour with a non-licensed person contrary to OPDP-10 SAT UNSAT N/A COMMENTS:_________________________
END OF TASK STOP TIME
Admin RO Ala PAGE 4
OF 4
Class Room ANSWER KEY INITIAL CONDITIONS:
3 licensed personnel are returning to shift from rotating assignments and are reactivating their licenses. The following table gives information as to hours worked under direction of an activated licensee, tours performed, etc.
Pre activation Shift Shift Shift Shift Performance License Meeting 1
Shift 2 3
Shift 4 5
6 Plant Tour Step Ups Training 12 hrs 12 his 12 his 12 hrs 12 his 12 his Per SM instructions Does Not Ro1 Manager IJ-3 U-3 RU U-i tagging U-2 U-2 conducted complete Meet Shift Manager RU RU UO RU RU RU plant tour with STA (SRU)
Ups Training 12 his 12 his 12 his 12 his l2hrs Per SM instructions Meets Manager U-2 U-2 RU U-i U-3 RU U-3 conducted complete requirements Ups RU Called for RU RU plant tour with extra R02 Superintendent Random Drug RU assigned to that test during shift shift crew missed end of shift turnover Ups Training 12 his 12 his 12 his 12 his 12 his Conducted complete Does Not Manager U-2 U-2 RU U-3 U-3 RU U-i plant tour with U.-2 RB Meet R03 Ups RU RU RU AUU Superintendent INITIATING CUE:
The Shift Manager has tasked you to determine which of the personnel, if any, have completed the requirements for license reactivation. If any personnel do not meet the requirements for license reactivation state the reason(s) why.
Admin SRO Ala PAGE 1
OF 4
OPERATOR:
RO___
SRO DATE:
JPM NUMBER:
Admin SRO Ala TASK NUMBER:
U-000-AD-17 TASK TITLE:
Determine Adequate Performance of License Reactivation K/A NUMBER: 2.1.4 K/A RATING:
SRO 3.8 TASK STANDARD: Determine which of the reactivating personnel have correctly completed the reactivation requirements.
LOCATION OF PERFORMANCE:
Class Room REFERENCES/PROCEDURES NEEDED: OPDP-lO VALDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS:
SATISFACTORY___
UNSATISFACTORY SIGNATURE:__________________
DATE:
EXAMINER
INITIAL CONDITIONS:
6 off-shift licensed personnel are returning to shift from rotating assignments and are reactivating their licenses. The following table gives information as to hours worked under direction of an activated licensee, tours performed, etc.
Pre-activation License Meeting Shift 1 Shift 2 Shift 3 Shift 4 Shift 5 Shift 6 Plant Tour Ops Training 12 hrs 12 hrs 12 hrs 12 firs Conducted Manager U-I U-2 SRO U-2 SRO U-2 SRO complete plant SROI Ops SRO tour with SM Superintendent Ops Training 12 firs 12 firs 12 hrs 12 firs Per SM Manager U-2 U-2 SRO U-3 SRO STA instructions Ops SRO conducted SRO2 Superintendent complete plant tour with Outside US (SRO)
Per SM Ops Training 12 hrs 12 12 hrs 12 12 instructions conducted Manager U-i U-I U-i U-2 WCC SRO 3 0l SRO SRO SRO SRO SRO complete plant Superintendent tour with STA (SRO)
INITIATING CUE:
The Shift Manager has tasked you to determine which of the personnel, if any, have completed the requirements for license reactivation. If any personnel do not meet the requirements for license reactivation state the reason(s) why.
Admin SRO Ala PAGE 3
OF 4
START TIME____
Performance Step 1:
Critical X Not Critical Analyzes information provided to determine which personnel meet the requirements for license reactivation.
Standard:
Determines SRO 1 and 3 meet the requirements for license reactivation.
SAT UNSAT N/A COMMENTS:
Performance Step 2:
Critical Not Critical States the reason why SRO2 does not meet the requirements for license reactivation.
Standard:
SRO 2 did not complete shift 5 under the supervision of an active licensed individual in the position (Shift Manager or Unit Supervisor as applicable for SROs), therefore he did not meet his 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> requirement SAT UNSAT N/A COMMENTS:_____
END OF TASK STOP TIME
Admin SRO Ala PAGE 4
OF 4
Class Room ANSWER KEY INITIAL CONDITIONS:
6 licensed personnel are returning to shift from rotating assignments and are reactivating their licenses. The following table gives information as to hours worked under direction of an activated licensee, tours performed, etc.
Pre-activation Shift Shift Shift Shift Shift Shift Performance License Meeting 1
2 3
4 5
6 Plant Tour Step Ops Training 12 his 12 hrs 12 his 12 his Conducted complete plant tour Meets SRO1 Manager U-I U-2 U-2 U-2 ith SM requirements Ops Superintendent SRO SRO SRO SRO Ops Training 12 his 12 his 12 his 12 his Per SM instructions conducted Does Not Meet SRO2 Manager U-2 U-2 U-3 STA complete plant tour with Ops Superintendent SRO SRO SRO Outside US (SRO)
Meets OpsTraining l2hrs l2hrs l2hrs l2hrs i2hrs PerSMinstructions requirements SRO 3 Manager U-i U-i U-i U-2 WCC conducted complete plant tour Ops Superintendent SRO SRO SRO SRO SRO with STA (SRO)
INITIATING CUE:
The Shift Manager has tasked you to determine which of the personnel, if any, have completed the requirements for license reactivation. If any personnel do not meet the requirements for license reactivation state the reason(s) why.
Admin RO Alb PAGE 1
OF 10 OPERATOR:
RO___
SRO___
DATE:________
JPM NUMBER:
Admin RO Aib TASK NUMBER:
Conduct of Operations TASK TITLE:
2-SR-2 ICS Computer points KIANTJMBER: 2.1.19 KIA RATING: RO 3.9 TASK STANDARD: Perform Operator logs using ICS screens in accordance with 2-SR-2 Instrument Checks and Observations for log tables 1.1, 1.6, 1.25, and 1.30.
Verify acceptance criteria are satisfied in accordance with notes.
LOCATION OF PERFORMANCE:
Unit 2 Simulator (ICS computer terminal)
REFERENCES/PROCEDURES NEEDED: 2-SR-2 Rev 71 VALIDATION TIME: 20 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS:
SATISFACTORY___
UNSATISFACTORY SIGNATURE:
DATE:
EXAMINER
INITIAL CONDITIONS: You are a Unit Operator assigned to Unit 2, and it is Friday morning at 0800. 2-SR-2, Instrument Checks and Observations, is being performed. All 2-SR-2 instrument checks and observations are complete with the exception of table 1.1, 1.6, 1.25, and 1.30.
INITIATING CUE: The Unit Supervisor directs you as the Unit Operator to complete 2-SR-2 for tables 1.1, 1.6, 1.25 and 1.30, utilizing only the ICS computer to obtain data
Admin RO Aib PAGE 3
OF 10 Simulator INITIAL CONDITIONS: You are a Unit Operator assigned to Unit 2, and it is Friday morning at 0800. 2-SR-2, Instrument Checks and Observations, is being performed. All 2-SR-2 instrument checks and observations are complete with the exception oftable 1.1, 1.6, 1.25, and 1.30.
INITIATING CUE: The Unit Supervisor directs you as the Unit Operator to complete 2-SR-2 for tables 1.1, 1.6, 1.25 and 1.30, utilizing only the ICS computer to obtain data
START TIME____
Admin RO Aib PAGE 4
OF 10 Performance Step 1:
Critical X Not Critical Refers to 2-SR-2, Instrument Checks and Observations, table 1.1 TA&E 1.1 CORE ThERMAL POWER AND CORE POWER DISTRtBUTION DAY SHIFT Weie APPIJCASIIJTh:
Model &titn 25% RTP Record the reactnqs soon os pcsib4e aftei the generstor brsoker hos been dosed.
Critetis Sourte:
32t1: 3.221: 32.3 DEFINmONS SECTION U
- FSAR &77 LOCATION:
ICSC--nputer (Ce Sunnry - CSUfl Reii.ew mutate Core Percetit TIh Thetmt Power LIMIT MFLCPR MAPRAT DIRX LIMF Unit DAY Note 2 Power (MWt)
(% RTP)
(AC)
(Note 3)
(Note 3)
(Note 3)
(AC)
Operstor Unit Surer 0800 1000 1200 Fnday 1600 1800 0800 1000 F__
1600 j__
Notes o5tJ3 1&2 3,4,&5 1000 1600 1800 0800 1000 MoodaY-g 1600 1800 NOThS ARE FOUOMNG ThE TABLE!
Standard:
Selects SR-2 Group Display from the Group Display menu OR types the code CSUM on ICS computer to obtain data and completes table 1.1 Data for Friday at 0800, Records 3456 for MWt, 100% for RTP,.899 for MFLCPR,.672 for MAPRAT and.769 for MFDLRX SAT UNSAT N/A COMMENTS:_____________________________
Admin RO Aib PAGE 5
OF 10 Performance Step 2:
Critical X Not Critical (I)
Compliance with the Licensed Power Limit (LPL) (3458 Mwt) is demonstrated by the following process:
A.
No actions are allowed that would intentionally raise core thermal power above 3458 Mwt for any period of time. Small, short-term fluctuations in power that are not under the direct control of the unit operator are not considered intentional.
B.
Closely monitor the thermal power during steady-state power operation with the goal of maintaining the two-hour average at or below 3458 Mwt. If the core thermal power average for a 2-hour period is found to exceed 3458 Mwt, Operations take timely action to ensure that thermal power is less than or equal to 3458 MWt.
(This isimplemented by taking action when any running average less than or equal to the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> average exceeds 3458 Mwt.)
C.
The core thermal power for an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period ( 8 hr average) is not to exceed 3458 Mwt.
D.
If an evolution is expected to cause a transient increase in reactor power that could exceed 3458 Mwt, action should be taken to lower core power prior to performing the evolution.
E.
IF power is > 3463, REDUCE power.
F.
IF power is 3458 to 3463 MWt after allowing time for recent perturbations to settle, REDUCE power and EVALUATE the trend.
G.
IF any running 30 mm Avg, 1 hr average, or 2 hr average is> 3458 MWt, REDUCE power.
(2)
Core Thermal Power is normally recorded every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when required. However, these readings may be marked N/A during TIP trace runs, control rod pattern adjustments, or anytime Core Monitoring System is blocked andlor < 25%
power. The Reactor Engineer is responsible for monitoring Core Thermal Limits. Monitoring of Core Thermal Power and other Core Thermal Limits is recommended following completion of planned rise in power and following any unexpected power change. If core monitoring software becomes unavailable, the Unit Supervisor/SRO and Reactor Engineer shall determine the appropriate frequency for monitoring Core Thermal Power but should not exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, using backup core monitoring computer, and taking into consideration current core conditions and margin to thermal limits. Power changes should not normally be made without the core monitoring software being available.
(3)
A. Consult the Reactor Engineer when value 0.955. Refer to 0-TI-248 for Administrative Limits.
B. Consult the Reactor Engineer when value 0.83 5. Refer to 0-TI-248 for Administrative Limits.
C. Consult the Reactor Engineer when value 0.985. Refer to 0-TI-248 for Administrative Limits.
(4)
If any Turbine Bypass valve(s) are inoperable or a Recirculation Loop is out of service, contact the Reactor Engineer and refer to the COLR for Turbine Bypass Out of Service (TBOOS) or Single Loop Operation (SLO) limits which must be applied.
(5)
MAPRAT within limits is used to verify that all APLHGRs are within the limits specified within the COLR, and <.850.
MFDLRX within limits is used to verify that all LHGRs are within the limits specified within the COLR.
MFLCPR within limits is used to verify that all MCPRs are within the limits specified within the COLR, and <.970 when core thermal power is > 90% RTP.
Standard:
Initial for Unit Operator for Friday at 0800 when acceptance criteria is verified in accordance with above notes.
SAT USAT N/A COMMENTS:_____________________________
Admin RO Aib PAGE 6
OF 10 Performance Step 3:
Critical X Not Critical Refers to 2-SR-2, Instrument Checks and Observations, table 1.6 cmt! Qut:
2ER9E14 c%a,ai; Rrdei-flitSt I.2 Vei HI RI HI tz h
MAX 0EV TIe 1.B1 P I..2 re N0Ted. INc 1
,4EA F) 34Br
-EA1 C)
MOI7 MI 2 OAT! UtATJ MA UO Oupvr FrM Oftty 21Ina Mny TLedy WeOO7 Thwl Standard:
Selects SR-2 Group Display from the Group Display menu OR types the specific codes for each ICS point into the Single Value Display (for example: 3-48A, 3-48B, etc...) and completes table 1.6 Data for Friday. Records 377.2 for listed ICS points TABLE t.
HEAT BAL.NCE RBLATE GO AlARM DETOINTO Ntz I DAY HIF WE UCABILTI:
Wdg! iten OE%
O to SAT UNSAT N/A COMMENTS:
Admin RO Aib PAGE 7
OF 10 Performance Step 4:
Critical X Not Critical (1)
The computer points listed in Table I.B. 1 and I.B.2 are inputs to the ICS Core Thermal Power Heat Balance calculations. The points are monitored to ensure the inputs are in agreement and to ensure the license limits for thermal power are maintained. In addition to the above, these points should be monitored any time reactor power changes are performed.
(2)
A difference between Feedwater temperature points 3-48A, 3-48B, 3-50A, 3-50B, and NSSOOI7 of greater than 2 degrees will require the notification of Site Engineering and suspending any rise in power until the discrepancy is resolved.
(3)
An alarm setpoint being exceeded will require notifying the Unit Supervisor immediately and, if action cannot be taken immediately to return the value to within limits, Site Engineering will be notified for assistance.
TABLE l.Bi ICS POINT DESCRIPTION HI ALARM HI HI ALARM CALCO2O Rx Power 30 Mm Avg.
3458 3483 CALCO21 Rx Power 1 Hr. Avg.
3458 3461 CALCO83 Rx Power 2 Hr. Avg.
3458 3459 CALCOQ8 Generator Power 1185 1190 CALCO26 Efficiency 3-5 36 CALCO27 LoadLe WA 113.6 CALCO24 Rx Power %
100.2 100.5 TABLE I2 ICS POINT DESCRIPTION HI ALARM HI HI ALARM 3-48A FW Temp 362 385 3-4S FW Temp 386 3-50A FW Temp 362 385 3-50 FW Temp 382 386 NS000I7 A. FWTernp.
382 386 CONS000 Ta RWCU Flow 0.15 WA Standard:
Documents Sat and initials for Unit Operator for Friday when Maximum Deviation between Feedwater temperature computer points are within 2 degrees (Note 2) and the conditions ofNote 3 are satisfied lAW with tables 1.B. 1 and 1.B.2.
SAT_ UNSAT N/A _COMMENTS:___________________________
Admin RO Aib PAGE 8
OF 10 Performance Step 5:
Critical X Not Critical Refers to 2-SR-2, Instrument Checks and Observations, table 1.25 TA&E125 LPR&4INQTUMENTATION 03.YSHIFT WEEX.
b______________
APPUCABIUTY:
MoSeE I & 2 Readingo ate teqrtfed at alt tmeo.
Crierla Creoie:
Te4ttnC3t N ernetse Manual TSR 3.3.5.3 LOCATION:
Pallet 2-lt-14 oSS lCD Computer Reelew tiltats C LPRL4O BYPASSED Notel TotaiC 001LPRM realtflgs APRU LPRM APRM LPRM APRM LPRM APRM LPRM Sypaosed 3% mi ICS MAX DElI AS Data DAY TIME
- 2
- 2
- 4
- 4
- 3
- 3
- 5
- 5 tNDe2) tNole3)
AC SATIUNSAT UO U#2Svr Frtoay 5805 S3Mm 0800 Sunday 5800 Nosday 5800 Ttrez4ay 0800 Wedneeda5 0805 TtaIr05ay 5805 Standard:
Clicks on Live LPRM Display in the Nuclear Heat Balance menu and completes table 1.25 Data for Friday, #LPRMs reading 3% on ICS. Records ZERO SAT_ UNSAT N/A Performance Step 6:
Critical X Not Critical (1)
Record number of LPRMs bypassed in the four APRM and LPRM cabinets as observed at Panel 2-9-14.
add these values together and record as Total # LPRMs Bypassed.
(2)
Less than 20 LPRMs in OPERATE or Less than 3 per level for any APRM will result in a Rod Block and a trouble alarm on the display panel. This does not yield an automatic APRM trip, but does, however, make the associated APRM INOP.
(3)
Record number of LPRMs reading less than 3% on the LPRM printout or display on ICS.
(4)
MAX DEV is not required to be met when the APRMs are downscale; however, unexpected inconsistencies should be reported to the Reactor Engineer. The total number of LPRMs bypassed shall equal the number of LPRMs reading less than 3% on ICS.
Standard:
Documents Sat and initials for Unit Operator for Friday when the conditions ofNote 4 are satisfied.
SAT_ UNSAT N/A _COMMENTS:
Admin RO Aib PAGE 9
OF 10 Performance Step 7:
Critical X Not Critical Refers to 2-SR-2, Instrument Checks and Observations, table 1.30 T40LE 1.00 REACTOR 40S2EL STEAM SOME PRESSURE INSTRUMENTATION DAY SHIFT WEEK APFLICAEILTTY:
Modes I a 2 ReadIngs ane reqExeO 11 all 5455.
5545155005 RequIrlWsn15:
3.2.1.1.1(03). 3.3.3.1.1. 3.4.10.1 LOCATION:
ISO (Note 1 54) 2446 2-945 2-544 2-9-03 REVIEW InItialS MAX S
C 8
A L5)C 55terence TL%IE 5EV 5EV MAX
.55 Data Leg
)541e4) 3-74A 3-788 (AC) 24(5-3-220 2-PIS-3-22C 2415-3-2288 2-P(5-3-22AA (AC)
LIMIT SATIIJNSAT US Un5OLw PriSsy 0-500 Slrday 0500 Sunday 0800 4Op 50 p519 Note 3 (N0t521
)340752)
NoteS Tuesday 0802 WedOesday 0802 Thursday 0.500 Standard:
Selects SR-2 Group Display from the Group Display menu OR types the specific codes for each ICS point into the Single Value Display (for example: 3-74A, 3-74B, etc...) and completes table 1.30 Data for Friday. Records approximately 1050 psig for ICS point 3-74A and approximately 1005 psig for ICS point 3-74B.
SAT UNSAT N/A _COMMENTS:
Admin RO Aib PAGE 10 OF 10 Performance Step 8:
Critical X Not Critical (1)
These readings may be obtained from ICS using the Single Value Display or from the ATU output voltage translated into a PRESSURE Signal for the specific instruments. For ICS, type in SVD for Single Value Display, enter the point desired as 3-74K, record reading, select F4, enter 3-74B, record the second reading.
(2) 3-74A and 3-74B have a Maximum allowable deviation of 40 psig, AND 2-PIS-3-22D, -PIS-3-22C, 2-PIS-3-22BB, & 2-PIS-3-22AA, have a Maximum allowable deviation of 60 psig. No comparison is required between the 3-74A(B) and 2-PIS-3-22D(C)(BB)(AA).
(3) 3-74A and 3-74B SI-IALL be 1050 psig. 2-PIS-3-22D, 2-PIS-3-22C, 2-PIS-3-22BB, & 2-PIS-3-22AA SHALL be 1090 psig.
(4) 3-74A and 3-74B are to be recorded at 0800. The Auxiliary Instrument Room readings are not required to be taken at precisely 0800.
(5)
Following a change to Reactor Power and/or Pressure, verifi the Steam Dome Limits are within the 0-TI-248, Administrative Limits and Design Analysis Limits (Appendix S)
Standard:
Reviews notes and documents UNSAT and initials for Unit Operator for Friday when the conditions ofNotes 2 and 3 are reviewed.
SAT_ U1JSAT N/A COMMENTS:_______
END OF TASK STOP TIME
Surveillance Procedure Data Package Modes 1, 2- £ CORE THERMAL POWER AM) CORE DOWER DISTRIBUTION ThI.sweeI Ne)ctweeJ.
APPLICABILITY:
Mode 1 wfleri 2% R I P Record :fle readings as soai as ps9bIe alter t[le generator breaIr has been closed Criteria S3urce:
32.1.1; 3.2.2.; 32.1; DEFINITIONS SECTION 1.1
- FSAR 3.7.7 I OCATION ICS Conpilter (Case Sinimary - CSLJM)________
Review lnitiflls Corc Percent TIME Thcrnial Power LIMIT MFLCPR MAPRAT MFDLIV<
LIMIT Unt DAY Note 2 Power 1Jt 1% RTP (AC)
(Note 1 A (Note l rn (N&e (AC)
Onerator Unit Supvr 0800 100.0 I
0.44 0.02 o.xq 1000 1200 Friday 1400 1600 1800 0800 1000 1200 Saturday 1400 1600 1800 Notes Notes 0800 1&2 3,4,&5 1000 Sunday 1600 1200 0800 1000 Monday 1600 1800 TABLE 1.1 DAY SI4IFT WEEK:
NOTES APE FOLLOWING THE TABLEI
- ANSWER KEY *********************
Admin RO Aib Unit 2 BFN Instrument Checks and Observations 2-SR-2 Unit 2 Rev. 0072 Page 23 of 149 Attachrnent2 (Page 3 of 87)
Surveillance Procedure Data Package - Modes 1, 2, & 3 (1)
Compliance with the Licensed Power Limit (LPL) (3458 Mwt) is demonstrated by the following process:
A.
No actions are allowed that would intentionally raise core thermal power above 3458 Mwt for any period of time. Small, short-term Iluctuations in power that are not under the direct control of the unit operator are not considered intentional.
B.
Closely monitor the thermal power during steady-state power operation with the goal of maintaining the two-hour average at or below 3458 Mwt.
If the core thermal power average for a 2-hour period is found to exceed 3458 Mwt, Operations take timely action to ensure that thermal power is less than or equal to 3458 MWt. (This is implemented by taking action when any running average less than or equal to the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> average exceeds 3458 Mwt.)
C.
The core thermal power for an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period ( 8 hr average) is not to exceed 3458 Mwt, D.
if an evolution is expected to cause a transient increase in reactor power that could exceed 3453 Mwt, action should be taken to lower core power prior to perfrming the evolution.
E.
IF power is > 3463, REDUCE power.
F.
IF power is 3458 to 3463 MWt after allowing time for recent perturbations to settle, REDUCE power and EVALUATE the trend.
G.
IF any running 30 mm Avg. 1 hr average, or 2 hr average is > 3450 MWt, REDUCE power.
(2)
Core Thermal Power is normally recorded every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when required. However, these readings may be marked NIA during TIP trace runs, control rod pattern adjustments, or anytime Core Monitoring System is blocked and/or < 25% power. The Reactor Engineer is responsible for monitoring Core Thermal Limits. Monitoring of Core Thermal Power and other Core Thermal Limits is recommended following compfetion of planned rise in power and following any unexpected power change. If core monitoring software becomes unavailable the Shift Manager and Reactor EngIneer shall determine the appropriate frequency for monitoring Core Thermal Power but should not exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, using backup core monitoring computer, and taking into consideration current core COnditions and margin to thermal limits. Power changes should not normally be made without the core monitoring software being available.
(3)
A.
Consult the Reactor Engineer when value 0.955. Refer to O-Tl-248 for Administrative Limits.
B.
Consult the Reactor Engineer when value 0.835. Refer to O-Tl-248 for Administrative Limits.
C.
Consult the Reactor Engineer when value 0.985. Refer to 0-11-248 for Administrative Limits.
- ANSWER KEY *********************
Admin RO Aib Unit 2 BFN Instrument Checks and Observations 2-SR-2 Unit2 Rev, 0072 Page 31 of 149 (Pa9e Ii of 87)
Surveillance Procedure Data Package - Modes 1, 2, & 3 TABLE 1.6 HEAT BALANCE RELATED ICS ALARM SETPOINTS (Note 1)
DAY SHIFT WEEK:
APPLICABILITY:
Mode 1 when 25% RTP Recocd the readings as soon as possible after the generator breaker has been closed.
Criteria Source:
BFPER95I9I4 LOCATION:
ICS Computer Review lniials I CS Points HI and HI HI aIam setpoints listed in 3-48A 3-485 3-50A 3-505 NSSOOI7 MAX Table 1.5.1 & 1.5.2 are NOT exceeded (Note 3)
Unit (F
(°fl (P1 FF1 DEV SAT! UNSAT I NIA
[IC) upvr Friday f7.2 I
Saturday Sunday rF Monday (Note 2)
Tuesday Wednesday Thursday The conputer points listed in Table LB. I and 1.8.2 are inputs to the ICS Core Thermal Power Heat Balance calculations. The points are monitored to ensure the inputs are in agreement nd to ensure the license limits for thermal power are maintained. In addition to the above, these points should be monitored any time reactor power changes are performed.
A difference between Feedwater temperature points 3-48A. 3-488. 3-50k 3-508. and NSSOO17 of greater than 2 degrees will require the notification of S4te Engineering and suspending any rise iii power unlil the discrepancy is resolved.
An alarm setpoint being exceeded will require notifying the Unit Supervisor immediately and. if action cannot be taken immediately to. return the value to within limits. Site Engineering will be notified for assistance.
TABLE 1.8.1 TABLE 1.2 ThIs weeI
- t. Ne)t weeI.
(1)
(2)
(3)
ICS POINT DESCRIPTION HI ALARM HI HI ALARM CALCO2[)
Rx Power 30 Mm Avg.
3458 3463 CALCO21 Rx Power 1 Hr. Avg.
3458 3451 CALCO83 Rx Power 2 Hr. Avg.
3458 3450 CALCOO8 Generator Power 1185 1190 CALCO26 Effidency 35 36 CALCO27 Load Line N/A 113.6 CALCO24 Rx Pr%
100.2 100.5 ICS POINT DESCRIPTION HI ALARM HI HI ALARM 3-48A FwTemp 382 388 3-488 FWTemp 382 388 3-50A FWTemp 382 388 3-SOB FW Temp 382 388 NSSOO17 Avg FW Temp.
382 388 CONSO400 Total RWCU Flow 0.15 N/A
- ANSWER KEY *********************
Admin RO Aib Unit 2 BFN Instrument Checks and Observations 2-SR-2 Unit2 Rev. 0072 Page 48 of 149 (Page 28 of 87)
Surveillance Procedure Data Package - Modes 1, 2, & 3 APPLICABILITY:
Modes I & 2 Readings are required at all times.
V Criteria Source:
Technical Requirements Manual TSR 3.3.5.3 LOCATION:
Panel 2-0-14 and ICS Computer Review Initials
- LPRMs BYPASSED Total #
- of LPRM LPRMs readings APRM LPRM APRM LPRM APRM LPRM APRM LPRM Bypassed 3% on ICS MAX 0EV All Data DAY TIME
- 2
- 2
- 4
- 4
- 3
- 3
- 1
- 1 (Note 2)
(Note 3)
(AC)
SATIUNSAT UO Unit Supvr Friday 0800 0
0 0
0 0
0 0
0 0
SAT isiSé Saturday 0800 Sunday 0800 0
Monday 0800 (Note 4)
Tuesday 0800 Wednesday 0800 Thursday 0800 (1)
Record number of LPRMs bypassed in the four APRM and LPRM cabinets as observed at Panel 2-9-14. Add these values together and record as Total # LPRMs Bypassed.
(2)
Less than 20 LPRMS in OPERATE or Less than 3 per level for any APRM will result in a Rod Block and a trouble alarm on the display panel. This does not yield an automatic APRM trip, but does, however, make the associated APRM INOP.
(3)
Record number of LPRMs reading less than 3% on the LPRM printout or display on ICS.
V (4)
MAX 0EV is not required to be met when the APRMs are downscale; hover, unexpected inconsistencies should be reported to the Reactor Engineer. The total number of LPRMS bypassed shall equal the number of LPRMS reading less than 3% on ICS.
TABLE 1.25 LPRM INSTRUMENTATION DAY SHIFT WK:
ThI.s weeJ.
Ne?& weel.
to
AdminROAlbUnit2 BFN Instrument Checks and Observations 2-SR-2 Unit2 Rev. 0072 Page 54 of 149 (Page 34 of 87)
Surveillance Procedure Data Package - Modes 1, 2, & 3 ThIsweeJ?.
Ne)ctweel TABLE 130 REACTOR VESSEL STEAM DOME PRESSURE INSTRUMENTATION DAY SHIFT WEEK:
to APPUCABILIT(:
Modes 1 & 2 Readings are required at all times.
Surveillance Requirements:
3.31.1. 1(f3), 3.3.3.1.1. 3.4.10.1 LOCATION:
ICS (Note I & 4) 2-0-88 2-0-85 2-9-84 2-9-83 Review Initials 4.X D
C B
A MAX Reference TIME 0EV 0EV MAX All Data Leg (Note 4) 3-74A 3-74B (AC) 2-PIS-3-22D 2-PlS-3-22C 2-PIS-3-22BB 2-PIS-3-22M (AC)
LIMIT SATIUNSAT UO Unit;Supvr Friday 0800 1OO lOOc iOc iOc iO3c 103S inUals Saturday 0800 Sunday 0800 Month 0800 40 psig 60 psig Note 3
(Note 2)
(Note 2)
Note 5 Tuesday 0800 Wednesday 0800 Thursday 0800 (1)
These readings may be obtained from ICS using the Single Value Oispiay from the ATU output voltage translated into a PRESSURE Signal for the specific instrurnemts.
For ICS, type in SVD for Single Value Display, enter the point desired as 3-74A, record reading, select F4. enter p3-748, record the second reading.
(2) 3-74A and 3-748 have a Maximum allowable deviation of 40 psig, AND 2-PIS-3-22D, 2-PIS-3-22C 2-PIS-3-2288 & 2-PIS-3-22AA, have a Maximum allowable deviation of 60 psig. No comparison is required between the 3-74A(8) and 2-PIS-3-22D(C)(8B)(AA).
(3) 3-74A and 3-748 SHALL be 1050 psig. 2.PIS-3-22D, 2-PIS-3-22C, 2-PIS-3-2288, & 2-PIS-3-22AA SHALL be 1090 psig.
(4) 3-74A and 3-748 are to be recorded at 0800. The Auxiliary Instrument Room readings are not required to be taken at precisely 0800.
(5)
Following a change to Reactor Power or Pressure, verify the Steam Dome limits are within the 0-11-248, Administrative Limits and Design Analysis limits (Appendix S
- Student Handout *********************
Admin RO Aib Unit 2 BFN Instrument Checks and Observations 2-SR-2 Unit 2 Rev. 0072 Page 21 of 149 CORE THERMAL POWER AND CORE POWER DISTRIBUTION AI+LICI1JILI IV:
Wode 1 when 25% RTP Record Itie readings as socn as possible alter the generator breaker has been closed Criteria SDurce:
32.i.1;3.2.2.i;_323.1; DEFINITIONS SECTION 11-FSAR 3.7.7 I OCATIC)N ICS computer (Case Summary -_CStiM________
Review InitiflIs Core Percent TIME Thermal Power LIMIT MFLCPR M?iPRAT MDLRX LIMIT Unit DAY Note 2 Power (MWt)
(% RTP)
(AC)
Note 3.A)
Note 3.S)
(Note 3C)
(AC)
Operator Un Supvr U8UU 1000 1200 Finidy 1400 1600 1800 0800 1000 1200 Saturday 1400 1600 1800 Notes Notes 0800 1&2 3,4,&5
- 1000 Sunday 1600 1800 0000 1000 Monday 1600 1ann TABLE 1i (Page 1 of 87)
Surveillance Procedure Data Package
= Modes 1, 2, & 3 IDAY SHIFT 11ilsweeI.
Nextwe&.
ft.
NOTES ARE FOLLOWING THE TABLE!
- StudentHandout*********************
AdminROAlbUnit2 BFN Instrument Checks and Observations 2-SR-2 Unit2 Rev. 0072 Page 23 of 149 (Page 3 of 87)
Surveillance Procedure Data Package - Modes 1, 2, & 3 (1)
Compliance with the Licensed Power Limit (LPL) (3458 Mwt) is demonstrated by the following process:
A.
No actions are allowed that would intentionally raise core themial power above 3456 Mwt for any period of time. Small, short-term fluctuations in power that ar not under the direct control of the unit operator are not considered intentional.
5.
Closely monitor the thermal power during steady-state power operation with the goal of maintaining the two-hour average at or below 3458 Mwt.
If the core themial power average for a 2-hour period is found to exceed 3458 Mwt, Operations take timely action to ensure that thermal power is less than or equal to 3458 MWt. (This is implemented by taking action when any running average less than or equal to the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> average exceeds 3458 Mwt)
C.
The core thermal power for an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period ( 8 hr average) is not to exceed 3458 MWL D.
If an evolution is expected to cause a transient increase in reactor power that could exceed 3458 Mwt, action should be taken to lower core power prior to perfrrning the evolution.
E.
iF power is > 3463, REDUCE power.
F.
IF power is 3458 to 3463 MWt after allowing time for recent perturbations to settle, REDUCE power and EVALUATE the trend.
G.
IF any running 30 mm Avg. 1 hr average, or 2 hr average is > 3450 MWt, REDUCE por.
(2)
Core Thermal Power is normally recorded every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when required. However, these readings may be marked NIA during TIP trace runs, control rod pattern adjustments, or anytime Core Monitoring System is blocked and/or < 25% power. The Reactor Engineer is responsible for monitoring Core Themial Limits. Monitoring of Core Themial Power and other Core Themial Limits is recommended following comp{etion of planned rise in power and following any unexpected power change. If core monitorirg software becomes unavailable, the Shift Manager and Reactor Engineer shall determine the appropriate frequency for monitoring Core Thermal Power but should nut exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, using ba.ckup core monitoring computer, and taking into consideration current core conditions and margin to thermal limits. Power changes should not nornally be made without the core monitoring software being available.
(3)
A.
Consult the Reactor Engineer when value 0.955. Refer to O-TI-248 for Administrative Limits.
S.
Consult the Reactor Engineer when value 0.835. Refer to O-Tl-248 for Administrative Limits.
C.
Consult the Reactor Engineer when value 0.985. Refer to O-TI-248 for Administrative Limits.
- Student Handout *********************
Admin RO Aib Unit 2 BFN Instrument Checks and Observations 2-SR-2 Unit 2 Rev. 0072 Page 31 of 149 (Page 11 0187)
Surveillance Procedure Data Package - Modes 1, 2, & 3 TABLE 1.6 HEAT BALANCE RELATED ICS ALARM SETPOINTS (Note 1)
DAY SHIFT WEEK:
APPLICABILITY:
Mode I when 25% RTP Recofd the readings as soon as possible after the generator breaker has been closed.
Criteria Source:
BFPER9519I4 LOCATiON:
ICS Computer Review Initials ICS Points HI and HI HI alarm setpoints listed in 3-48A 3-488 3-50A 3-5DB NSSOO17 MAX Table 1.6.1 & 1.B2 are NOT exceeded. (Note 3)
Unit (CF)
(DF)
(°F)
(F)
(F)
DEV SAT! UNSAT I N/A UO
$upvr Friday Saturday Sunday 2F Monday (Note 2)
Tuesday Wednesday Thursday The computer points listed in Table 1.8.1 and 1.8.2 are inputs to the lCS Core Thermal Power Heat Balance calculations. The points are monitored to ensure the inputs are in agreement nd to ensure the license limits for thermal power are maintained. In addition to the above, these points should be monitored any time reactor power changes are performed.
A difference between Feedwatec temperature points 3-48A. 3-48B. 3-50A. 3-50B. and NSSOO17 of greater than 2 degrees viuI require the notification of Site Engineering and suspending ny rise in power until the discrepancy is resolved.
An alarm se(point being exceeded will require notifng the Unit Supervisor immediately and. if action cannot be taken imediately to. return the value to witNn limits. Site Engineering 6II le notified for assistance.
TA3L 1.3.2 ThLc weeI NextweeJ.
(1)
(2)
(3)
TABLE 1.3.1 ICS POINT DESCRIPTION HI ALARM HI HI ALARM CLCO20 Rx Power 30 Mm Avg.
3458 3463 CALCO21 Rx Power 1 Hr. P.vg.
3458 3461 CALCO83 Rx Power 2 Hr. Avg.
3458 3450 CALCO98 Genexator Power 1185 1190 CALCO26 Efficiency 35 36 CALCO27 Load Line N/A 113.8 CALCO24 Rx Pcwer%
1002 100.5 ICS POINT DESCRIPTION HI /LARM HI HI ALARM 3-48A FWTemp 382 386 3488 FW Temp 382 388 3-SOA FWTemp 382 388 3-SOB FW Temp 382 388 NSSOO17 Avg.. FW Temp.
382 386 CONSO400 Total RWCU Flow 0.15 N/A
- Student Handout *********************
Admin RO Aib Unit 2 BFN Instrument Checks and Observations 2-SR-2 Unit2 Rev 0072 Page 48 of 149 (Page 28 of 87)
Surveillance Procedure Data Package - Modes 1, 2, & 3 APPUCABILITY:
Modes I & 2 Readings are required at all times.
Criteria Source:
Technical Requirements Manual TSR 33&.3 LOCATION:
Panel 2-9-14 and ICS Computer Review Initials
- LPRMS BYPASSED ToiaI#
- ofLPRM
° LPRMS readings APRM LPRM APRM LPRM APRM LPRM AFRM LPRM Bypassed 3% on ICS MAX 0EV All Data DAY TIME
- 2
- 2
- 4
- 4
- 3
- 3
- 1
- 1 (Note 2)
(Note 3)
(AC)
SATIUNSAT UO Unit Supvr Friday 0800 0
0 0
0 0
0 0
Saturday 0800 Sunday 0800 Monday 0800 (Note 4)
Tuesday 0800 Wednesday 0800 Thursday 0800 (1)
Record number of LPRMS bypassed in the four APRM and LPRM cabinets as observed at Panel 2-9-14. Add these values together and record as Total # LPRMs Bypassed.
(2)
Less than 20 LPRMS in OPERATE or Less than 3 per level for any APRM will result in a Rod Bloclc and a trouble alarm oa the display panel. This does not yield an automatic APRM Uip, but does, however, make the associated APRM INOP.
(3)
Record number of LPRMs reading less than 3% on the LPRM printout or display on IC&
(4)
MAX DEV is not required to be met when the APRMs are downscale; however, unexpected inconsistencies sticuld be reported to the Reactor Engineer. The total nurnbør of LPRMS bypassed shall equal the number of LPRMs reading less than 3% on ICS TABLE 1.25 LPRM INSTRUMENTATION DAY SHIFT WEEK:
ThIsweek Ne)tweel.
- StudentHandout*********************
AdminROAlbUnit2 BFN Instrument Checks and Observations 2-SR-2 Unit 2 Rev. 0072 Page 54 of 149 (Page 34 of 87)
Surveillance Procedure Data Package
- Modes 1, 2, & 3 i1iI.sweel.
TABLE 1.30 REACTOR VESSEL STEAM DOME PRESSURE INSTRUMENTATION DAY SHIFT WEEK:
to__________
APPLICABILITY:
Modes 1 & 2 Readings are required at all times.
Surveillance Requirements:
3.3.1.1.1(tS), 3.3.3.1.1,3.4.10.1 LOCATION:
ICS (Note 1 & 4) 2-0-88 2-0-85 2-0-84 2-0-83 Review Initials MAX D
C B
A MAX Reference TIME 0EV 0EV MAX All Data Leg (Note 4) 3-74A 3-748 (AC) 2-PIS-3-220 2-PIS-3-22C 2-PIS-3-22BB 2-PiS-3-22M (AC)
LIMIT SATIUNSAT UO Unit Supvr Friday 0800 103S 1D3 103c 103c Saturday 0800 Sunday 0800 Monda 0800 40 psig 80 psig Note 3 (Note2)
(Note2)
Note 5 Tuesday 0800 Wednesday 0800 Thursday 0800 (1)
These readings may be obtained from ICS using the Singia Value Display from the ATU output voltage translated into a PRESSURE Signal for the specific instruments.
For 1CS, type in SVD for Single Value Display, enter the point desired as 3-74A, record reading, select F4. enter p3-748, record the second reading.
(2) 3-74A and 3-746 have a Maximum allowable deviation of 40 psig AND 2-P1S-3-22D 2 PiS-3-22C 2-PIS-3-2256 & 2-PIS-3-22AA, have a Maximum allowable devration ol 60 psig. No comparison is required between the 3-74A(B) and 2-PIS-3-220(C)(85)(AA).
(3) 3-74A and 3-745 SHALL be 1050 psig. 2-PIS-3-22D, 2-PIS-3-22C, 2-PIS-3-225B. & 2-PIS-3-Z2AA SHALL be 1090 psig.
(4) 3-74A and 3-745 are to be recorded at 0800. The Auxiliary Instrument Room readings are not required to be taken at precisely 0800.
(5)
Following a change to Reactor Power or Pressure, verify the Steam Dome Limits are within the 0-Tl-248, Administrative Limits and Design Analysis Urnits (Appendix 5)
Admin RO Alb PAGE 1
OF 10 OPERATOR:
RO___
SRO___
DATE:________
JPMNUMBER:
AdminROAlb TASK NUMBER:
Conduct of Operations TASK TITLE:
3-SR-2 ICS Computer points KIANTJMBER: 2.1.19 KIA RATING: RO 3.9 TASK STANDARD: Perform Operator logs using ICS screens in accordance with 3-SR-2 Instrument Checks and Observations for log tables 1.1, 1.6, 1.25, and 1.30.
Verifi acceptance criteria is satisfied in accordance with notes.
LOCATION OF PERFORMANCE:
Unit 3 Simulator (ICS computer terminal)
REFERENCES/PROCEDURES NEEDED: 3-SR-2 Rev 68 VALIDATION TIME: 20 minutes MAX. TiME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS:
SATISFACTORY___
UNSATISFACTORY SIGNATURE:
DATE:
EXAMThER
INITIAL CONDITIONS: You are a Unit Operator assigned to Unit 3, and it is Friday morning at 0800. 3-SR-2, Instrument Checks and Observations, is being performed. All 3-SR-2 instrument checks and observations are complete with the exception oftable 1.1, 1.6, 1.25, and 1.30.
INITIATING CUE: The Unit Supervisor directs you as the Unit Operator to complete 3-SR-2 for tables 1.1, 1.6, 1.25 and 1.30, utilizing only the ICS computer to obtain data
Adrnin RO Aib PAGE 3
OF 10 Simulator INITIAL CONDITIONS: You are a Unit Operator assigned to Unit 3, and it is Friday morning at 0800. 3-SR-2, Instrument Checks and Observations, is being performed. All 3-SR-2 instrument checks and observations are complete with the exception oftable 1.1, 1.6, 1.25, and 1.30.
INITIATING CUE: The Unit Supervisor directs you as the Unit Operator to complete 3-SR-2 for tables 1.1, 1.6, 1.25 and 1.30, utilizing only the ICS computer to obtain data
START TIME____
Admin RO Alb PAGE 4
OF 10 Performance Step 1:
Critical X Not Critical Refers to 3-SR-2, Instrument Checks and Observations, table 1.1 IASLE 1.1 CCE 3)4L ?DWER AN POWER DI3TRjBUT1OM Standard:
nrc,,
DAY SHIFT Selects SR-2 Group Display from the Group Display menu OR types the code CSUM on ICS computer to obtain data and completes table 1.1 Data for Friday at 0800, Records 3456 for MWt, 100% for RTP,.878 for MFLCPR,.780 for MAPRAT, and.854 for MFDLRX SAT UNSAT N/A COMMENTS:
APPUCASILTY:
dt 1 ftefl 25% RTP e1e,-TQ PSL 2Le, 3.A3 RECORD 11W redw, DO1
- 1bt 5tflt et Ocd.
C5l 25Wt:
32l.1: 32.2.1; 3231: OEF1N1T1ON ECTION 1.1 -FDAR.7.7 LCCAT1C4:
C4I54,ter Ce 3unrnary -C3UM)
T CcThef Pcc,,tP5r LIMIT MFLR MAPRAT MDLRX LWt URt tWIt DAY Ncte2 Power 4AWl 4% RTP)
AC Nc 3 3
I4t 3 4AC Oef DUw 1oo 1253 1333 0333 1033 1233 1333
i No1e 32 1033 1233 1433
Admin RO Aib PAGE 5
OF 10 Performance Step 2:
Critical Not Critical (1)
Compliance with the Licensed Power Limit (LPL) (3458 Mwt) is demonstrated by the following process:
A.
No actions are allowed that would intentionally raise core thermal power above 3458 Mwt for any period of time. Small, short-term fluctuations in power that are not under the direct control of the unit operator are not considered intentional.
B.
Closely monitor the thermal power during steady-state power operation with the goal of maintaining the two-hour average at or below 3458 Mwt. If the core thermal power average for a 2-hour period is found to exceed 3458 Mwt. Operations take timely action to ensure that thermal power is less than or equal to 3458 MWt.
(This isimplemented by taking action when any running average less than or equal to the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> average exceeds 3458 Mwt.)
C.
The core thermal power for an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period ( 8 hr average) is not to exceed 3458 Mwt.
D.
If an evolution is expected to cause a transient increase in reactor power that could exceed 3458 Mwt, action should be taken to lower core power prior to performing the evolution.
E.
IF power is > 3463, REDUCE power.
F.
IF power is 3458 to 3463 MWt after allowing time for recent perturbations to settle, REDUCE power and EVALUATE the trend.
G.
IF any running 30 mm Avg, 1 hr average, or 2 hr average is> 3458 MWt, REDUCE power.
(2)
Core Thermal Power is normally recorded every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when required. However, these readings may be marked N/A during TIP trace runs, control rod pattern adjustments, or anytime Core Monitoring System is blocked and/or < 25%
power. The Reactor Engineer is responsible for monitoring Core Thermal Limits. Monitoring of Core Thermal Power and other Core Thermal Limits is recommended following completion of planned rise in power and following any unexpected power change. If core monitoring software becomes unavailable, the Unit Supervisor/SRO and Reactor Engineer shall determine the appropriate frequency for monitoring Core Thermal Power but should not exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, using backup core monitoring computer, and taking into consideration current core conditions and margin to thermal limits. Power changes should not normally be made without the core monitoring software being available.
(3)
A. Consult Reactor Engineer when value 0.965. Refer to 0-TI-248 for Administrative Limits.
B. Consult Reactor Engineer when value 0.835. Refer to 0-TI-248 for Administrative Limits.
C. Consult Reactor Engineer when value 0.985. Refer to 0-TI-248 for Administrative Limits.
(4)
If any Turbine Bypass valve(s) are inoperable or a Recirculation Loop is out of service, contact the Reactor Engineer and refer to the COLR for Turbine Bypass Out of Service (TBOOS) or Single Loop Operation (SLO) limits which must be applied.
(5)
MAPRAT within limits is used to verify that all APLHGRs are within the limits specified within the COLR, and
<0.850.
MFDLRX within limits is used to verify that all LHGRs are within the limits specified within the COLR.
MFLCPR within limits is used to verify that all MCPRs are within the limits specified within the COLR, and < 0.980 when thermal power is> 90% RTP.
Standard:
Initial for Unit Operator for Friday at 0800 when acceptance criteria is verified in accordance with above notes.
SAT UNSAT N/A _COMMENTS:
Admin RO Aib PAGE 6
OF 10 Performance Step 3:
Critical X Not Critical Refers to 3-SR-2, Instrument Checks and Observations, table 1.6 TABLE 1 NEAT BALANCE REL4.T 103 ALARM 0ETOINT3 Nte DAY HIFT W!E(
APUCABILJTY:
Made I Iien RTPToP&LQ3A 0ti 3ot:
BPERS114 LOVAT10:
3 ntfr jy 103 Vtf HI H HI Ii N 1tAXD Tt4E 1.B1 a 1.9.: e NTteted. Nc Urt 3-4a.4 F) a4as r 3-3AF 3E N03t017 (Fl Ncdt 2 3AT: LIt43ATJ NA UO Suw Fl4y 8ftai 3un4 My TUeIt WeY TI.wj Standard:
Selects SR-2 Group Display from the Group Display menu OR types the specific codes for each ICS point into the Single Value Display (for example: 3-48A, 3-48B, etc...) and Completes table 1.6 Data for Friday. Records 377.2 for listed ICS points SAT UNSAT N/A COMMENTS:
Admin RO Aib PAGE 7
OF 10 Performance Step 4:
Critical X Not Critical (1)
The computer points listed in Table 1.B.1 and l.B.2 are inputs to the ICS Core Thermal Power Heat Balance calculations. The points are monitored to ensure the inputs are in agreement and to ensure the license limits for thermal power are maintained. In addition to the above, these pothts should be monitored any time reactor power changes are performed.
(2)
A difference between Feedwater temperature points 3-48A, 3-48B, 3-50A, 3-50B, and NSSOO17 of greater than 2 degrees will require the notification of Site Engineering and suspending any rise in power until the discrepancy is resolved.
(3)
An alarm setpoint being exceeded will require notifiing the Unit Supervisor immediately and, if action cannot be taken immediately to return the value to within limits, Site Engineering will be notified for assistance.
TABLE 1.8:
ICS POINT DESCR1PTION HI ALARM HI HI ALARM CALCO2O R Power 30 Mm Avg.
3452 3483 CALCO2I Rx Power 1 Hr. Avg.
3458 3461 CALCO23 Rx Power 2 Hr. Avg.
3458 3450 CALCO8 GeneratorPower 1185 iio CALCO26 Effioenoy 35 38 CALCO27 Load Le NIA 113.6 CALCO24 Rx Power %
100.2 100.5 TASLE 1.B.2 ICS POINT DESCRIPTION HI ALARM HI HI AL4RM 3-48A FW Ten 382 328 3-488 FW Temp 382 388 3-50A FWTemp 382 398 3-508 FW Ten, 382 328 NSSOO17 Avg. FW Temp.
382 388 CONSO400 Tot3I RWCU Flow 0.188 N!A Standard:
Documents Sat and initials for Unit Operator for Friday when Maximum Deviation between Feedwater temperature computer points are within 2 degrees (Note 2) and the conditions of Note 3 are satisfied JAW with tables 1.B.1 and 1.B.2.
SAT UNSAT N/A COMMENTS:___________________________
Admin RO Aib PAGE 8
OF 10 Performance Step 5:
Critical X Not Critical Refers to 3-SR-2, Instrument Checks and Observations, table 1.25 TABLE 1.25 LPM INSTUUENTATI0N DAY SHIFT 18004 APPLIGAB)LIEY:
Modes I E 2 ReadasEs ae qu at I emes.
eferto PSI Step 3A)
Ciltena Senrse:
Te&noaI Requwements Manod TSR 3.3,5.3 LOCATION P,et 3-5-14 and CS Ccnpder Ren*w lnd)als
- LPRMs BYPASSED (Note 1)
TotaId
- IPRMS
LPRMs seadn MAX 0EV APR88 LPRM APRM 1RPM APRM 1RPM APPM 1RPM Bypassed 3%ontCS (AC)
ASDuta DAY TIME 02
- 2 04 04 03 03
- 1
- 1 (NoIe2(
(ftote3)
(Noie4(
SAT/UNSAT UO UndSw Fnday 0803 Satoday 0800 Sunday 0800 Monday 0800 0
Tuesday 0800 Wesesdoy 0800 Thursday 0800 Standard:
Clicks on Live LPRM Display in the Nuclear Heat Balance menu and completes table 1.25 Data for Friday, #LPRMs reading 3% on ICS. Records ZERO SAT UNSAT N/A COMMENTS:_______________________________
Performance Step 6:
Critical X Not Critical (1)
Record number of LPRMs bypassed in the four APRM and LPRM cabinets as observed at Panel 3-9-14.
add these values together and record as Total # LPRMs Bypassed.
(2)
Less than 20 LPRMs in OPERATE or Less than 3 per level for any APRM will result in a Rod Block and a trouble alarm on the display panel. This does not yield an automatic APRM trip, but does, however, make the associated APRM INOP.
(3)
Record number of LPRMs reading less than 3% on the LPRM printout or display on ICS.
(4)
MAX DEV is not required to be met when the APRMs are downscale; however, unexpected inconsistencies should be reported to the Reactor Engineer. The total number of LPRM t
s bypassed shall equal the number of LPRMs reading less than 3% on ICS.
Standard:
Documents Sat and initials for Unit Operator for Friday when the conditions of Note 4 are satisfied.
SAT_ UNSAT N/A COMMENTS:
Admin RO Aib PAGE 9
OF 10 Performance Step 7:
Critical X Not Critical Refers to 3-SR-2, Instrument Checks and Observations, table 1.30 TABLE 1.30 REACTOR VESSEL STEAM DOME PRESSURE INSTRUMENTATiON DAY SHIFT APPLICABILITY:
Mories I 82 (Refer To P8). Step 3.EA)
Rea&ngs are required at af tunes.
Sureedlanne Requrenents:
&3.111(i3L 3.3.3.).?. 3.410.?
LOCATION:
CS (Notes 1 84; 34-88 3-9-85 3-9-84 3-9-83 Resiew Iridats MAX 0
C B
A MAX Reference tIME 0EV 0EV MAX A9Da Leg (NOte 4) 3-74A 3-745 (AC) 3-PIS-3-220 3-F(S-3-22C 3-PIS-3-22EB 3-PIS-3-229A (AC)
LIMIT SATIJNSAT UO Unit Supw Friday 0900 Saturday 0800 Sunday 0800 4
Opsig itOpsig (NoIe3)
Monday 0500
(Note 2)
(Note 2)
(Note 5)
Tuesday 0000 We88esday 0000 Thursday 0800 Standard:
Selects SR-2 Group Display from the Group Display menu OR types the specific codes for each ICS point into the Single Value Display (for example: 3-74A, 3-74B, etc...) and completes table 1.30 Data for Friday. Records approximately 1050 psig for ICS point 3-74A and approximately 1005 psig for ICS point 3-74B.
SAT UNSAT N/A COMMENTS:____________________________
Admin RO Aib PAGE 10 OF 10 Performance Step 8:
Critical Not Critical (1)
These readings may be obtained from ICS using the Single Value Display or from the ATU output voltage translated into a PRESSURE Signal for the specific instruments. For ICS, type in SVD for Single Value Display, enter the point desired as 3-74A, record reading, select F4, enter 3-74B, record the second reading.
(2) 3-74A and 3-74B have a Maximum allowable deviation of 40 psig, AND 3-PIS-3-22D, 3-PIS-3-22C, 3-PIS-3-22BB, & 3-PIS-3-22AA, have a Maximum allowable deviation of 60 psig. No comparison is required between the 3-74A(B) and 3-P1S-3-22D(C)(BB)(AA).
(3) 3-74A and 3-74B SHALL be S 1050 psig. 3-PIS-3-22D, 3-PIS-3-22C, 3-PIS-3-22BB, & 3-PIS-3-22AA SHALL be 1090 psig.
(4) 3-74A and 3-74B are to be recorded at 0800. The Auxiliary Instrument Room readings are not required to be taken at precisely 0800.
(5)
Following a change to Reactor Power and/or Pressure, verif, the Steam Dome Limits are within the 0-TI-248, Administrative Limits and Design Analysis Limits (Appendix 5)
Standard:
Reviews notes and documents UNSAT and initials for Unit Operator for Friday when the conditions of Notes 2 and 3 are reviewed.
SAT_ UNSAT N/A _COMMENTS:_______
END OF TASK STOP TIME
- ANSWER KEY *********************
Admin RO Aib Unit 3 BFN Instrument Checks and Observations 3-SR-2 Unit 3 Rev. 0068 Page 20 of 146 (Page 1 of 86)
Surveillance Procedure Data Package - Modes 1, 2, & 3 TABLE 1.1 CORE THERMAL POWER AND CORE POWER DISTRIBUTION DAY SHIFT WEEK:
Thts week to__ week APPLICABILITY:
Mode 1 when 25% RTP (Refer To P&L Step 3.GA)
RECORD the readings as soon as possible after the generator breaker has been closed.
Criteria Source:
32.1.1;_3.2.2.1; 3.2.3.1; DEFINITIONS_SECTION_1.1_-FSAR_3.7.7 LOCATION:
ICS Computer (Case Summary - CSUM)
Review Initials TIME Core Thermal Percent Power LIMIT MFLCPR MAPRAT MFDLRX LIMIT Unit Unit DAY Note 2 Power (MWI)
(% RTP)
(AC)
Note 3 Note 3 Note 3 (AC)
Operator Supvr 0800 400.0 0.ff 090 0.QcL 1000 1200 Friday 1400 1600 1800 0800 1000 1200 Saturday 1400 1600 1800 Notes 0800
&2 3,4,&
1000 1200 Sunday 1400 1600 1800 0800 1000 1200 Monday 1400 1600 1800 NOTES ARE FOLLOWING HE TABLE!
- ANSWERKEY*********************
AdminROAlbUnit3 BFN Instrument Checks and Observations 3-SR-2 Unit 3 Rev. 0069 Page 22 of 146 (Page ot86)
SurveilLance Procedure Data Package - Modes 1, 2, & 3 (1)
Compliance with the Licensod Power Limit (LPL) (3458 Mwt) is demonstrated by the following process:
A.
No actions are allowed that would intentionally raise core thermal power above 3458 Mwt for any period of time. Sm all, short-term fluctuations in power that are not under the direct control of the unit operator are not considered intentional.
B.
Closely monitor the thermal power during steady-state power operation with the goal of maintaining the two-hour average at or below 3458 Mwt. If the core thermal power average for a 2-hour period is found to exceed 3458 Mwt. Operations take timely action to ensure that thermal power is less than or equal to 3458 MWt. (This is implemented by taking action when any running average less than or equal to the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> average exceeds 3458 MwlL)
C.
The core thermal power for ar 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period ( 8 hr average) is not to exceed 3458 Mwt.
D.
If an evolution is expected to cause a transient increase in reactor power that could exceed 3458 Mwt, action should be taken to lower core power prior to performing the evolution.
E.
IF power is> 3403. REDUCE power.
F.
IF power is 3458 to 3463 MWt after allowing time for recent perturbations to settle. REDUCE power and EVALUATE the trend.
G..
IF any running 30 mm Avg. 1 hr average, or 2 hr average is >3458 MWI. REDUCE power.
(2)
Core Thermal Power is normally recorded every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when required. However, these readings may be marked NJA during TIP trace runs, control rod pattern adjustments, or anytime Core Monitoring System is blocked andtor <25% power. The Reactor Engineer is responsible for monitoring Core Thermal Limits. Monitoring of Core Thermal Power and other Core Thermal Limits is recommended following completion of planned rise in power and following any unexpected power change.
If core monitoring software becomes unaailable-, the Unit SupervisoriSRO and Reactor Engineer shall determine the appropriate frequency for monitoring Core Thermal Power but should not exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, using backup core monitoring computer, and taking into consideration current core conditions and margin to thermal limits. Power changes should not normally be made without the core monitonng software being available, (3)
A.
Consult Reactor Engineer when value 0.Q65. Refer to O-Tt.248 for Administrative Limits.
B Consult Reactor Engineer when value 0.835. Refer to 0-T1-248 for Administrative Limits.
C.
Consult Reactor Engineer when value 0.Q85. Refer to 0-11-248 for Administrative Limits.
(4)
If any Turbine Bypass valve(s) are inoperable or a Recirculation Loop is out of service, contact the Reactor Engineer and refer to the COLR for Turbine Bypass Out of Service ([BOOS) or Single ioop Operation (SLO) limits which must be applied.
(5)
MAPRAT within limits is used to verify that all APLHGRs are within the limits specified within the COIR. and 0.850.
MFDLRX withrn limits is use.d to verify that all LHGRS are within the limits specified within the COI.R.
MFLCPR within Limits is used to verify that all MCPRs are within the limits specified within the COLR. and 0.8O when core thermal power is 90% RTP.
- ANSWER KEY *********************
Admin RO Aib Unit 3 BFN Instrument Checks and Observations 3-SR-2 Unit 3 Rev. 0068 Page 29 of 146 (Page 10 of 86)
Surveillance Procedure Data Package Modes 1, 2, & 3 TABLE 1.6 HEAT BALANCE RELATED ICS ALARM SETPOINTS (Note 1)
DAY SHIFT WEEK:
APPLICABILITY:
Mode 1 wtien 25% RTP(Refer To P&L Step 3.6A)
RECORD the readings as soon as possible after the generator breaker has been closed.
Criteria Source:
BFPER951914 LOCATION:
ICS Computer Review Initials ICS Points Verify HI and HI HI alarm setpoints listed in MAX DEV Table 1.8.1 & 1.B.2 are NOT exceeded. (Note 3)
Unit 3-48A (°F) 3-488 (°F) 3-50A (°F) 3-50B (°fl NSSOO1 7 (°F)
Note 2 SAT! UNSAT I NIA UO Supvr Friday 17)2 17)2 fl2 SAT F
TJfS4S Saturday Sunday Monday 2°F Tuesday Wednesday Thursday The computer points listed in Table 1.8. 1 and 1.8.2 are inputs to the lC Core Thermal Power Heat Balance calculations. The points are monitored to ensure the inputs are in agreement and to ensure the license limits for thermal power are maintained, In addition to the above, these points should be monitored any time reactor power changes are performed.
A difference between Feeciwater temperature points 3-48A, 3-488, 3-50A, 3-508, and NSSOOI7 of greater than 2 degrees will require the notification of Site Engineering and suspending any rise in power until the discrepancy is resolved.
An alarm setpoint being exceeded will require notifying the Unit Supervisor immediately and, if action cannot be taken immediately to return the value to within limits, Site Engineering will be notified for assistance.
TABLIZ 1.13:
TABLE 1.B.2 ilii.s weefr to Next weeI (1)
(2)
(3)
ICS POINT DESCRIPTION HI ALARM HI HI ALARM CALCO2O Rx Power 30 Mm Avg.
3458 3463 CALCO21 Rx Power 1 Hr. Avg.
3458 3461 CALCO83 Rx Power 2 Hr. Avg.
3458 3459 CALCO98 Generator Power 1185 1190 CALCO26 Efficiency 35 36 CALCO27 Load Line N!A 113.6 CALCO24 RxPower%
100.2 100.5 CS POINT DESCRIPTION HI ALARM HI HI ALARM 3-48A FW Temp 382 386 3-488 FW Temp 382 386 3-50A FW Temp 382 386 3-508 FW Temp 382 386 NSSOO17 Avg. FW Temp.
382 386 CONSO400 Total RWCU Flow 0.168 NIA
- ANSWER KEY *********************
Admin RO Aib Unit 3 BFN Instrument Checks and Observations 3-SR-2 I
Unita RevS 0068 L
Page4Gof 146 (Page 27 of 8)
SurveillanGe Procedure Data Package
- Modes 1, 2, & a (1)
Record number of LPRMS bypassed in the fourAPRM and LPRM cabinets as observed at Panel 34-14. add these values together and record as Total # LPRMs 8ypassed.
(2)
Less than 2Q LPRMs in OPERATE or Less than 3 per level for any APllM will result in a Rod Block and a trouble alami on the display panel. This does not yield an autorntic APRM Irip, but does, however, make the assockted APRM INOR (3)
Record number of LPRMs redin less than 3% on the LPRM pnatout or display on ICS.
(4)
MAX 0EV is not required to be met when the APRMs are downscale; however, unexpected inconsistencies should be reported to the Reactor Engineer. The total number of LPRMS bypassed shall equal the number of LPRMs read[ng less than 3% on ICS TABLE 125 LPRtI INSTRUMENTATION DAY SIIIFT WEEK:
Thi-s weeJ.
Nt week APPUCABIUTY:
Mode5 I 5 2 Readings. are required at alt times.
(Refer To. P&L Step 3.8A)
Criteria Source:
rechnical Requirements Manual TSR 33.5.3 LOCA11QN; Panel 3+14 and ICS Computer Review lnitJal
- LPRMs BYPASSED (Note I)
Total #
- LPRMs f
LPRMS reading MAX 0EV APRM IPRIM AFRM LPRM AFRM LPRM APRM LPRM Bypassed 3% an IGS (AC)
All Data DAY TIME
- 2
- 2
- 4
- 4
- 3
- 3
- 1
- 1 (Note 2)
(Note 3)
(Note 4)
SATIIJNSAT UO Unit Supvr Friday 0800 0
0 0
0 0
0 0
0 0
0 Saturday 0800 Sunday 0800 Monday 0800 0
Tuesday 0800 Wednesday 0800 Thursday 0800
- ANSWERKEY*********************
AdminROAlbUnit3 BFN Insirument Checks and Observations 3-SR-2 Unit 3 Rev. 0068 Page 52 of 146 (Page 33 of 86)
Surveillance Procedure Data Package - Modes 1, 2, & 3 ThIsweel.
Netwee TABLE 130 REACTOR VESSEL STEAM DOME PRESSURE INSTRUMENAI1ON DAY SHIFT WEE$
to APFUCABILrn:
Modes 1 & 2 (Refer To P&L Step 3.6A)
Readings are required at all times Suiveillance Requiremenis:
3.3.1. 1.1(f3). &3i.1. 3.4.10.1 LOCATION:
ItS (Notes 1 & 4) 2-9-86 3-9-85 34-84 3-9-83 Review Initials MAX D
C B
A MAX Reference TIME DEV 0EV MAX MI Data Le (Note 4) 3-74A 3-748 (AC) 3-P-3-22D 3-PIS-3-22C 3-PIS-3-22B8 3-PIS-3-22AA (AC)
LIMIT SAT11JNSAT UO Unit Supvr Friday 0800 10Sf) 1005 1035 1035 1035 1035 UNSAT iiiilals Saturday 0800 Sunday 0800 I4onda 0800 40 piy 00 pziy (NuLa 3)
(Note 2)
(Note 2)
(Note 5)
Tuesday 0800 Wednesday 0800 Thursda) 0800 (1)
These readings may be obtained from ICS using the Single Value Disçiay or from the ATU output voltage translated into a PRESSURE Sicnal for the specifc instruments.
For ICS, type in SVD for Single Value Display, enter the point desirec as 3-74A, record reading, select F4, enter 3-74B, record the second reading.
(2) 3-74A and 3-748 have a Maximum allowable deviali00 of 40 psig, AND 3-PIS-3-22D, 3-PIS-3-22C, 3-PIS-3-2285, & 3-PIS-3-22AA, have a Maximum allowable deviation of 6Opsig. No coniprison is required 3etween the 3-74A(B) and 3-PIS-2-22D(C)(BB)(Mi.
(3) 3-MA and 3-748 S-fALL be 1050 sig. 3-PIS-3-22D, 3-PIS-3-22C, 3-PIS-3-2288, & 3-PIS-3-22AA S[-ALL be 1090 psig.
(4) 3-7 4A and 3-745 are to be recorded at 0800. The Aueiuiary Instrument Room readings are not required b be taken at preDisely 0800.
(5)
Fdlowing a change to Reactor Power and/or Pressure, verify the Steam Dome Limits tie within the 0-Tl-248, Administratve Limits and Design Analysis Limits (Appendix S)
STUDENT HANDOUT Admin RO Aib Unit 3 BFN Instrument Checks and Observations 3-SR-2 Unit 3 Rev. 0068 Page 20 of 146 (Page 1 of 86)
Surveillance Procedure Data Package Modes 1, 2, & 3 WEEK:
ThLs wee1, Ne.xt weeI to TABLE II CORE THERMAL POWER AND CORE POWER DISTRIBUTION DAY SHIFT APPLICABILITY:
Mode 1 when 25% RTP (ReterTo P&L Step 3.6A)
RECORD the readings as soon as possible after the generator breaker has been dosed.
Criteria Source:
32.11;_3.22.1;_3.2.31;_DEFINITIONS_SECTION_11_-_FSAR 3.71 LOCATION:
ICS Computer (Case Summary
- CSUM)
Review Inttials TIME Core Thermal Percent Power LIMIT MFLCPR MAPRAT MFDLRX LIMIT Unit Unit DAY Note 2 Power (MWt)
(% RTP)
(AC)
Note 3 Note 3 Note 3 (AC)
Operator Supvr 0800 1000 1200 Friday 1400 1600 1800 0800 1000 1200 Saturday 1400 1600 1800 Notes Notes 0800 5:
1000 1200 Sunday 1400 1600 1800 0800 1000 1200 Monday 1400 1600 1800 1
NOTES ARE F HE TABLE!
STUDENT HANDOUT Admin RO Aib Unit 3 BFN Instrument Checks and Observations 3-SR-2 Unit 3 Rev. 0069 Page 22 of 146 (Page 3 of 86)
Surveillance Procedure Data Package - Modes 1, 2, & 3 (1)
Corn p1lance with the Licensed Paier Limit (LPL) (3458 Mwi) is demonstrated by the following process:
A.
No actions are allowed that weuld intentionally raise core ttierrnal power above 3458 Mwt for any period of time. Small, short-term fluctuations in power that are not under the dhect control of the unit operator are not considered intentional.
B.
Closely monitor the thermal power during steady-state power operation 4th the goal of maintairdng the tw>-hour average at or bekv 34S8 Mwt. If the core thermal power average for a 2-hour petiod is found to exceed 3458 Mwt, Operations take timely action to ensure that thermal power is less than or equal to 3458 MWL (This is implemented by taking action when any rurriing average less than or equal to the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> average exceeds 3458 Mwt)
C.
The core themial power for an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period (8 hr average) is not to exceed 3458 Mwi.
D.
If an eIulion is expected to cause a transient increase in reactor power that could exceed 3456 Mwt, action shouki be taken to lower core power puor to peifomiing the evolution.
E.
IF power is> 3463, REDUCE power.
F.
IF power is 3458 to 3463 hVdVt after allowing lime for recent perturbations to settle, REDUCE power and EVALUATE the trend.
G.
IF any running 30 mm Avg, 1 hr average, or 2 hr average is> 3458 MWt, REDUCE power.
(2>
Core Thermal Power is normally recorded every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when reqttired. However, these readings may be rnar1ed NIA during liP trace runs, control rod pattern adjustments, or anytime Core Monitoring System is blocked and/or < 25% power. The Reactor Engineer is responsible for monitoring Core Thermal Limits. Monitoring of Core Thermal Power and other Core Thermal Limits is recommended following completion of planned nse in power and following any unexpected power change. If core monitoring softwere becomes unavailable, the Unit SupervisorlSRO and Reactor Engineer shall determine the appropriate frequency for monitoring Core Thermal Power but should not exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, using backup core monitoring computer, and taking into consideration current core conditions and margin to thermal limits. Power changes should not normally be made without the core monitoring software being available.
(3)
A.
Consult Reactor Engineer when value 0.965. Refer to 0-11-248 for Athrinislrative Limits.
B.
Consult Reactor Engineerwhen value 0.835. Refer to 0-11-248 for Athilnistrative Limits.
C.
Const Reactor Engineer when value 0.985. Refer to 0-11-248 for Adiuiinisfralive Limits.
(4)
If any Turbine 8ypass valve(s) are inoperable or a Recirculation Loop is out of service, contact the Reactor Engineer and refer to the COIR for Turbine B,pass Out of Service (TBOOS) or Single Loop Operation (SLO) limits which must be applied.
(5)
MAPRAT within limits is used to verify that all APLHGRS are within the limits specified within the COLR, and 0.850.
MFDLRX within limits is used to verify that all LHGRs are within the limits specified within the COIR.
MFLCPR within limits is used to verify that all MCPRS are within the limits specified within the COLR, and 0.980 when core thermal power is 90% RTP.
STUDENT HANDOUT Admin RO Aib Unit 3 BFN Instrument Checks and Observations 3-SR-2 Unit 3 Rev. 0068 Page 29 of 146 (Page 10 of 86)
Surveillance Procedure Data Package
- Modes 1, 2, & 3 APPLICABILITY:
Mode 1 when 25% RTP(ReferTo P&L Step 3.6A)
RECORD the readings as soon as possible alter the generator breaker has been closed.
Criteria Source:
BFPER951914 LOCATION:
ICS Computer Review Initials Ics points Verify HI and HI HI alarm setpoints listed in MAX DEV Table 1.8,1 & I.B.2 are NOT exceeded. (Note 3)
Unit 3-48A (°F) 3-488 (CF) 3-50A (°F) 3-508 (9Z)
NSSOO1 7 (CF)
Note 2 SAT! UNSAT I N/A UO Supvr Friday Saturday Sunday Monday 2F Tuesday Wednesday Thursday The computer points listed in Table 1.8.1 and 1.B.2 are inputs to the IC Core Thermal Power Heat Balance calculations. The points are monitored to ensure the inputs are in agreement and to ensure the license limits for themial power are maintained. In addition to the above, these points should be monitored any time reactor power changes are performed.
A difference between Feedwater temperature points 3-48A, 3-48B, 3-50A, 3-SOB, and NSSO0IT of greater than 2 degrees will require the notification of Site Engineering and suspending any rise in power until the discrepancy Is resolved.
An alarm setpoint being exceeded will require notiing the Unit Supervisor immediately and, if action cannot be taken immediately to return the value to within limits, Site Engineering will be notified for assistance.
TABLE 1.B.1 ICS POINT DESCRIPTION HI AI.ARM Hi HI ALARM CALCO2O Rx Power 30 Mm Avg.
3458 3463 CALCO2I Rx Power I Hr. Avg.
3458 3461 CALCO83 Rx Power 2 Hr. Avg.
3458 3459 CALCO98 Generator Power 1185 1190 CALCO26 Efficiency 35 36 CALCO27 Load Line N/A 113.6 CALCO24 RxPower%
100.2 100.5 ICS POINT DESCRIPTION Hi ALARM Hi HI ALARM 3-48A FW Temp 382 386 3-48B FWTemp 382 386 3-50A FW Temp 382 386 3-SOB FW Temp 382 386 NSSOOI7 Avg. FW Temp.
382 386 CONSO400 Total RWCU Flow 0.168 N/A TABLE 1.6 HEAT BALANCE RELATED ICS ALARM SETPOINTS (Note 1)
DAY SHIFT WEEK ThIswe&,
NextweeI to (1)
(2)
(3>
TABLE 1.B.2
STUDENT HANDOUT Admin RO Aib Unit 3 BFN Instrument Checks and Observations 3-SR-2 Unit 3 Rev. 0068 Page 46 of 146 TABLE 1.25 LPRM INSTRUMENTATION (Page 27 of 86)
Surveillance Procedure Data Package - Modes 1, 2, & 3 DAY SHIFT WEEK This weel Next weel.
(1)
Record number of LPRMS bypassed in the four APRM and LPRM cabinets as observed at Panel 3-9-14. add these values together and record as Total # LPRMs Bypassed.
(2)
Less than 20 LPRMS in OPERATE or Less than 3 per level for any APRM will result in a Rod Block and a trouble alarm on the display panel. This does not yield an aittornatic APRM trip, but does, however, make the associated APRM INOP.
(3)
Record number of LPRMs reading less than 3% on the LPRM printout or display on ICS.
(4)
MAX DEV is not required to be met when the APRMs are dowriscale; hover, unexpected inconsistencies should be reported to the Reactor Engineer. The total number of LPRMs bypassed shall equal the number of LPRMS reading less than 3% on ICS.
to APPUCABILITt:
Modos 1 & 2 Readings are required at all times.
(Refer Ta P&L Step 3MA)
Criteria Source:
Technical Requirements Manual TSR 3a5.3 LOCATION:
Panel 3-0-14 and IC Computer Review lnidals
- LPRMs BYPASSED (Note 1)
Total #
All Data DAY TIME
- 2
- 2
- 4
- 4
- 3
- 3
- 1
- 1 (Note 2)
(Now 3)
(Noto 4)
SATIUNSAT UO UnihSupvr Friday
[O I
° I
° I
° I
I I
° I
° Saturday 0800 Sunday 0800 Monday 0800 0
Tuesday 0800 Wednesday 0800 Thursday 0800
STUDENT HANDOUT Admin RO Aib Unit 3 BFN Instrument Checks and Observations 3-SR-2 Unit 3 Rev. 0068 Page 52 of 146 (Page 33 of 86)
Surveillance Procedure Data Package - Modes 1, 2, & 3 ykI,.cweek.
Nxtweel TABLE 1.30 REACOR VESSEL STEAM DOME PRESSURE INSTRUMENTATiON DAY SHIFT WEE(
_______________to APPIJCABILITY:
Modes I & 2 (Refr To P&L Step 3.A)
Readings are required at all times Suiveillance Reciuirements:
3.31.1.I(f3). 33.3.1.1. 3.4.10.1 LOCATlOt ICS (Notes I & 4) 39-86 34-85 3--84 3-9.83 Review Initials MAX 0
C 8
Reference TIME DEV 0EV MAX At Data Leg (Note 4)
-74A 3-74B (AC) 3-PIS-3-220 3-PIS-3-22C 3-PIS-3-22BB 3-PIS-3-22AA (AC)
LIMIT SAT)UNSAT UO Unit Supvr Friday 0800 103c 103c 103c Saturday 0800 Sunday 0800 0800
- 41) psig 60 psig (Note 3)
(No 2)
(Note 2)
(Nott 6)
Tuesday 0800 Wednesday 0800 Thursday 0800 (1)
These readings may be obtained from ICS using the Single Value Dispayorfron1 the ATU output voltage translated into a PRESSURE Signal for the specific instruments.
For ICS, type in SvD for Single Vakie Display, enterthe point desired as 3-74A, reccid reading, select F4, enter 3-74B, record the sec,nd reading.
(2) 3-74A and 3-748 hove a Maximum allowable deviation of 40 psig, ANC 3-PIS-3-22D, 3-IS-3-22C, 3-PIS-3-2255, & 3-PIS-3-22AA, have a Maximum allowthle deviation of 60 psig. No companson is required between the 3-74(B) and 3-PIS-3-22D(C)(88)(AA (3) 3-74A and 3-745 SHALL be 1050 psig. 3-PIS-3-22D, 3-PIS-3-22C, 3-PIS-3-22B8, & 3-PIS-3-22AA SHALL be 1090 psig.
(4) 3-74A and 3-748 are to be recorded at 0600W The Auciliaty Instrument Room readings are not required to be taken at precisely 0800.
(5)
Fc(lowing a change to Reactor Power andlor Pressure, verify the Stean Dome Limits are within the 0-TI-248, Administrative Limits and Design Analysis Limits (Appendix S)
Admin SRO Aib PAGE 1
OF 5
OPERATOR:
JPM NUMBER:
Admin SRO Alb TASK NUMBER:
Conduct of Operations TASK TITLE:
NRC Event Notification KIA NUMBER: 2.1.18 KIA RATING: SRO 3.8 TASK STANDARD: Determine NRC Event Notification requirements, Technical Specification actions required, and proper internal notifications.
LOCATION OF PERFORMANCE:
Class Room REFERENCES/PROCEDURES NEEDED: NPG-SPP-03.5 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED: 60 Minutes PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS:
SATISFACTORY___
UNSATISFACTORY SIGNATURE:
DATE:
EXAMINER
INITIAL CONDITIONS: Unit 3 is performing a normal Reactor Startup in accordance with 3-GOI-l00-1A, Unit Startup. Reactor Power is 5%, Reactor pressure is 980 psig, and core flow is 9.5% of rated core flow. A feedwater transient causes a spike in Reactor Power and an automatic Scram occurs. The Reactor Engineer informs you that Reactor Power peaked at 28% RTP.
INITIATING CUE: As the Shift Manager, evaluate these plant conditions and determine:
(1) all required Technical Specification actions; (2) the earliest required NRC notification; and (3) all required internal TVA notifications
Admin SRO Aib PAGE 3
OF 5
Class Room INITIAL CONDITIONS: Unit 3 is performing a normal Reactor Startup in accordance with 3-GOI-100-1A, Unit Startup. Reactor Power is 5%, Reactor pressure is 980 psig, and core flow is 9.5% of rated core flow. A feedwater transient causes a spike in Reactor Power and an automatic Scram occurs. The Reactor Engineer informs you that Reactor Power peaked at 28% RTP.
INITIATING CUE: As the Shift Manager, evaluate these plant conditions and determine:
(1) all required Technical Specification actions; (2) the earliest required NRC notification; and (3) all required internal TVA notifications
Admin SRO Aib PAGE 4
OF 5
START TIME____
Performance Step 1:
Critical X Not Critical Refers to Technical Specification Section 2.0 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow
<10% rated core flow:
THERMAL POWER shall be <25% RTP.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
Standard:
Determines that a safety limit was exceeded or violated, determines 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to restore compliance and insert all rods. Both actions are met and complete SAT UNSAT N/A COMMENTS:__________________________
Admin SRO Aib PAGE 5
OF 5
Performance Step 2:
Critical X Not Critical Evaluates NPG-SPP-03.5 Appendix A: 3.1.B 1 B.
The following criteria require 1 -hour notification:
1.
(Technical Specifications)
- Safety Limits as defined by the Technical Specifications which have been violated.
Standard:
Determines a 1-Hr Non-Emergency notification is required.
SAT_ UNSAT N/A _COMMENTS:_____________________________
Performance Step 3:
Critical X Not Critical Evaluates NPG-SPP-3.5 Appendix D, Site Event Notification Matrix Standard:
For an NRC ONE hour notification at a minimum, the applicant must determine the following five individuals are required to be notified:
Duty Plant Manager Plant Manager Operations Duty Specialist (ODS)
Site Vice President Corporate Duty Officer SAT_ UNSAT N/A _COMMENTS:________
END OF TASK STOP TIME
Admin RO/SRO A2 PAGE 1
OF 7
OPERATOR:
RO___
SRO DATE:________
JPM NUMBER:
Admin RO/SRO A2 TASK NUMBER:
U-066-NO-02 TITLE:
Evaluate Recombiner Performance KJA NUMBER:
2.2.44 KJA RATING: RO 4.2 SRO 4.4 TASK STANDARD: Evaluate Off-Gas Recombiner Performance. Determine that it meets Acceptance Criteria.
LOCATION OF PERFORMANCE: Classroom REFERENCES/PROCEDURES NEEDED:
3-01-66 VALIDATION TIME: 10 minutes MAX. TIME ALLOWED:
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS:
SATISFACTORY___
UNSATISFACTORY SIGNATURE:
DATE:
EXAMINER
INITIAL CONDITIONS: You are a Unit Operator, a startup is in progress on Unit 3. The Hydrogen Water Chemistry System is in service in accordance with 3-01-4, Hydrogen Water Chemistry System. The Off-Gas Preheater, Recombiner and SJAEs are in operation in accordance with 3-01-66, Off-Gas System, Section 5.0. The in-service steam jet is operating properly.
INITIATING CUE: The Shift Manager has directed you to perform 3-01-66, Section 6.1, Recombiner Performance Evaluation, and identify ifany actions are required. Conditions are as follows:
3-TI-66-75B 3-TRS-66-77A Center temp 3-TRS-66-77B Center temp 3-TI-66-75A 392 °F Core Thermal Power (MWth) 3400 MWth Percent Power (% RTP) 98%
3-H2R-66-96 operable
- both pens reading.26% H2 320°F 612°F 380°F
Admin RO/SRO A2 PAGE 3
OF 7
Classroom INITIAL CONDITIONS: You are a Unit Operator, a startup is in progress on Unit 3. The Hydrogen Water Chemistry System is in service in accordance with 3-01-4, Hydrogen Water Chemistry System. The Off-Gas Preheater, Recombiner and SJAEs are in operation in accordance with 3-01-66, Off-Gas System, Section 5.0. The in-service steam jet is operating properly.
iNITIATING CUE: The Shift Manager has directed you to perform 3-01-66, Section 6.1, Recombiner Performance Evaluation, and identify if any actions are required. Conditions are as follows:
3-TI-66-75A 392 °F Core Thermal Power (MWth) 3400 MWth Percent Power (% RTP) 98%
3-H2R-66-96 operable
- both pens reading.26% H2 3-TI-66-75B 3-TRS-66-77A Center temp 3-TRS-66-77B Center temp 320°F 612 °F 380°F
Admin RO/SRO A2 PAGE 4
OF 7
START TIME____
Performance Step 1:
Critical Not Critical X 6.1 Recombiner Performance Evaluation NOTES 1)
The production of hydrogen and oxygen in the reactor is dependent upon reactor power level and upon the amount of hydrogen injected by the Hydrogen Water Chemistry System if in service. Since the recombination of hydrogen and oxygen is exothermic, the operating temperature of the recombiner is also dependent upon power level and the status of the HWC System.
2)
Following startup, while still at low power, recombiner performance and hydrogen concentration should be closely monitored.
[1]
Perform a Recombiner Performance Evaluation as follows:
[1.1]
DETERMINE the in-service recombiner inlet temperature as indicated on RECOMBINER 3A(3B), INLET TEMP 3-TI-66-75A(B), Panel 3-9-53.
Standard:
Determines Recombiner 3A inlet temp 3-TI-66-75A, Panel 3-9-53 (from handout)
SAT_ IJNSAT N/A COMMENTS:_____________________________
Performance Step 2:
Critical Not Critical X
[1.2]
DETERMINE the in-service recombiner operating (center) temperature as indicated on RECOMBINER 3A13B TEMPERATURE recorder, 3-TRS 77, Panel 3-9-53.
Standard:
Determines the in-service recombiner operating (center) temperature as indicated on Recombiner 3A temperature recorder, 3-TRS-66-77, Panel 3-9-53 (from handout)
SAT UNSAT N/A COMMENTS:_____________________________
Admin RO/SRO A2 PAGE 5
OF 7
Performance Step 3:
Critical Not Critical
[1.3]
CALCULATE the temperature difference (AT) between the values obtained in Steps 6.1[1] and 6.1[2].
Standard:
Calculates Recombiner 3A inlet/center At and determines At is 220 °F SAT UNSAT N/A COMMENTS:_______________________________
Performance Step 4:
Critical Not Critical X
[1.4]
DETERMINE the reactor thermal power (MWt) from process computer.
Standard:
Determines reactor thermal power from the handout SAT UNSAT N/A COMMENTS:_____________________________
Performance Step 5:
Critical X Not Critical
[1.5]
USING Illustration 1, PLOT the corresponding point ofreactor power in MWt and AT.
Standard:
Using illustration 1, Plots corresponding point of reactor power (3400 MWth) and AT (220 °F),
OR Determines At corresponding to 3400 MWT is 187 °F, Calculation: AT = 0.055 °F per MWth 0.055 X 3400 = 187 and using illustrationiplots this corresponding point.
SAT UNSAT N/A COMMENTS:
Admin RO/SRO A2 PAGE 6
OF 7
Performance Step 6:
Critical Not Critical
[1.6]
VERIFY point on illustration 1 is above or equal to the appropriate line (HWC in service or HWC out of service)
Standard:
Determines from Illustration 1 that calculated At vs MWt plots ABOVE the HWC in Service line. Candidate may also use calculated AT from curve factor to determine that actual AT (220 °F) is well above the HWC in service line on graph SAT_ IJIJSAT N/A _COMMENTS:_______________________________
Performance Step 7:
Critical Not Critical X
[2]
IF the in-service recombiner performance is below the minimum allowable, THEN:
[2.1]
CHECK Off-Gas Preheater, Recombiner and SJAEs are in operation in accordance with Section 5.0.
Standard:
NA Recombiner performance is satisfactory SAT UNSAT N/A _COMMENTS:_____
END OF TASK STOP TIME
Admin RO/SRO A2 PAGE 7
OF 7
Illustration I (Page I ofl)
Recombine Performance Evaluation - AT to Reactor Power MWt HWC Out of SeMcG HWC In Servic 3500 Evaluation is satisfactory when intersection point of AT to Reactor Power is above the appropriate line.
For 3458mwt HWC in service HWC out of service AT 190°F AT 242°F CURVE FACTORS Normal Water Chemistry (NWC)
Hydrogen Water Chemistry (HWC)
AT = 0.070°F per MWt AT = 0.055°F per MWt 0
500 1000 1500 2000 2500 3000
Admin SRO A3 PAGE 1
OF 6
OPERATOR:
SRO___
DATE:
JPM NUMBER:
Admin SRO A3 TASK NUMBER:
Radiation Control TASK TITLE:
Radiation Exposure Limits under Emergency Conditions KIA NUMBER: 2.3.4 KJA RATING: SRO 3.7 TASK STANDARD: Determine stay time for an AUO to perform an emergency evolution due to radiation levels and authorize.
LOCATION OF PERFORMANCE:
Class Room REFERENCES/PROCEDURES NEEDED: EPIP 15 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED:
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS:
SATISFACTORY___
UNSATISFACTORY SIGNATURE:
DATE:
EXAMINER
INITIAL CONDITIONS:
Unit 2 is in a General Emergency and YOU are currently the Site Emergency Director. Because of the emergency, an emergency exposure in excess of 10 CFR 20.1201 limits is required to prevent damage to the Main Turbine. An AUO has volunteered to replace blown fuses in the EBOP DC control cabinet next to the MTOT on EL 586 in the Turbine Building. Radiation Protection Supervision states that the dose rate at the cabinet is 15 REMJhr and travel path dose rates are 10 REM/hr to and from the cabinet. It is estimated that it will take him 12 minutes of total travel time to and from the cabinet. The AUO has received 500 mrem TEDE, year to date, and he has been briefed of the radiological hazards associated with this evolution per appendix A of the applicable EPIP.
INITIATING CUE:
As the Site Emergency Director YOU, are directed to 1) determine how much dose can be authorized for the AUO to perform this mission, 2) determine how much time this AUO has to replace the fuses, without exceeding Emergency Dose Limits, and 3) complete all required paperwork to authorize the emergency exposure.
Admin SRO A3 PAGE 3
OF 6
Class Room INITIAL CONDITIONS:
Unit 2 is in a General Emergency and YOU are currently the Site Emergency Director. Because of the emergency, an emergency exposure in excess of 10 CFR 20.1201 limits is required to prevent damage to the Main Turbine. An AUO has volunteered to replace blown fuses in the EBOP DC control cabinet next to the MTOT on EL 586 in the Turbine Building. Radiation Protection Supervision states that the dose rate at the cabinet is 15 REM/hr and travel path dose rates are 10 REM/hr to and from the cabinet. It is estimated that it will take him 12 minutes of total travel time to and from the cabinet. The AUO has received 500 mrem TEDE, year to date, and he has been briefed of the radiological hazards associated with this evolution per appendix A of the applicable EPIP.
IMTIATING CUE:
As the Site Emergency Director YOU, are directed to 1) determine how much dose can be authorized for the AUO to perform this mission, 2) determine how much time this AUO has to replace the fuses, without exceeding Emergency Dose Limits, and 3) complete all required paperwork to authorize the emergency exposure.
Admin SRO A3 PAGE 4
OF 6
START TIME____
Performance Step 1:
Critical Not Critical Determine the radiation dose that he may receive to protect valuable property Standard:
Determines he may receive 10 REM to protect valuable property SAT UNSAT N/A COMMENTS:__________________________
Performance Step 2:
Critical Not Critical Determine the radiation dose that AUO may receive without exceeding 10 REM, based on previous exposure Standard:
Determines that the AUO may receive 9.5 REM, based on previous exposure of 500 mrem TEDE, year to date, to protect valuable property SAT UNSAT N/A COMMENTS:__________________________
NRC Information: Reference is EPIP 15 Section 343 CUE: Provide EPIP 15 Appendix B form which is partially completed
Admin SRO A3 PAGE 5
OF 6
Performance Step 3:
Critical X Not Critical Determines the amount of time the AUO has to replace the blown fuses without exceeding the 10 REM Emergency Exposure limit to protect valuable property, based on previous exposure and travel time Standard:
Determines that the AUO has 30 minutes to replace the blown fuses, without exceeding Emergency Exposure Limit of 10 REM (Including travel time and previous exposure), If calculated in hours
- 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> SAT UNSAT N/A COMMENTS:_________________________
Performance Step 4:
Critical Not Critical Completes Acknowledgment and Authorization to Exceed Occupational Dose Limits form Appendix B of EPIP 15 Standard:
Determines that as the Shift Manager and acting Site Emergency Director he can authorize the Emergency Dose SAT UNSAT N/A COMMENTS:_________________
NOTE: Critical Data on form is the authorized 10 Rem and Approval signature END OF TASK STOP TIME
Admin SRO A3 PAGE 6
OF 6
APPEN DIX B Page 1 of 1 ACKNOWLEDGMENT AND AUTHORIZATION TO EXCEED OCCUPATIONAL DOSE LIMITS READ THE FOLLOWING STATEMENT BEFORE SIGNING THIS FORM:
I acknowledge by signature on this form that I am volunteering for exposures in excess of 10 CFR 20.1201 limits and that I have been made aware through training or a briefing ofthe risks involved. Briefing material was presented from Appendix A of this procedure.
The persons listed below have acknowledged and volunteered to receive dose limits in excess of 1 OCFR2O. 1201 limits. Authorization is required by the Site Emergency Director to administer any emergency exposure limit. Authorization is acknowledged by Site Emergency Director signature on the bottom of this form.
Brief Description of Task:
Authorized by:
Site Emergency Director Time/Dare Name Employee Identification Signature Dose Limit (Pleae print Last First, MI)
Number (EIN)
(Rem) j AUO that volunteered 123-45-6789 LAST PAGE
Admin RO A4 PAGE 1
OF 7
OPERATOR:
RO SRO___
DATE:
JPM NUMBER:
Admin RO A4 TASK NUMBER:
U-000-EM-87 TASK TITLE:
EPIP-3, Appendix B, Unit Operator Notification KIA NUMBER: 2.4.43 KJA RATING: RO 3.2 TASK STANDARD: Completion of Emergency Call-out for TSC Manning LOCATION OF PERFORMANCE:
Simulator REFERENCES/PROCEDURES NEEDED: EPIP 3 VALIDATION TIME: 15 minutes MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)
PERFORMANCE TIME:
COMMENTS:
Additional comment sheets attached? YES NO RESULTS:
SATISFACTORY UNSATISFACTORY SIGNATURE:__________________
DATE:_______
EXAMINER
INITIAL CONDITIONS:
You are the Unit 1 Operator. Unit 2 was operating at 100% (BOL) when indications of a primary system leak into the Drywell developed. Conditions have continued to the point that the SED has declared an ALERT.
INITIATING CUES:
The SHIFT MANAGER has informed you that Unit 2 is in an ALERT status. The SHIFT MANAGER/SED directs you to COMPLETE APPENDIX B, Unit Operator NOTIFICATIONS and determine if a Fitness for Duty question is required.
Admin RO A4 PAGE 3
OF 7
Class Room INITIAL CONDITIONS:
You are the Unit 1 Operator. Unit 2 was operating at 100% (BOL) when indications of a primary system leak into the Drywell developed. Conditions have continued to the point that the SED has declared an ALERT.
INITIATING CUES:
The SHIFT MANAGER has informed you that Unit 2 is in an ALERT status. The SHIFT MANAGERJSED directs you to COMPLETE APPENDIX B, Unit Operator NOTIFICATIONS and determine if a Fitness for Duty question is required.
Admin RO A4 PAGE 4
OF 7
START TIME____
Performance Step 1:
Critical X Not Critical NOTE The Emergency Paging System (EPS) consists of a dedicated touch screen CRT.
Activation of any screen feature requires the user place their fingertip within the boundary of the select button and leave it there for at least 1 second. The CRT Screen will normally display a large rectangle that indicates that the paging system is available but currently inactive.
If the EPS fails to operate, contact the SM/SED immediately. Request that the ODS be contacted to initiate the system from his location.
1.0 Activate the Emergency Paging System (EPS) 1.1 PRESS the EPS CRT screen once to activate the paging options Standard:
OPERATOR activates the Emergency Paging System using the touch screen.
SAT UNSAT N/A COMMENTS:
Performance Step 2:
Critical Not Critical 1.2 PRESS the appropriate option as instructed by the SED
- PAGER TEST
- DRILL
- EMERGENCY
- STAGING AREA
- ABORT Standard:
Operator presses either DRILL or EMERGENCY.
SAT UNSAT N/A COMMENTS:
Admin RD A4 PAGE 5
OF 7
Performance Step 3:
Critical X Not Critical 1.3 PRESS the START button to initiate the option OR PRESS the ABORT button to deny the option request Standard:
Presses the START button.
SAT UNSAT N/A COMMENTS:__________________________
CUE:
Immediately after operator depresses the START button on the touch screen:
TIME COMPRESSION: 20 minutes has elapsed, provide candidate with Paging System Status Display Handout Performance Step 4:
Critical Not Critical 1.4 IF the EPS fails to operate locally THEN CONTACT the ODS at 5-751-1700 or 5-751-2495 AND DIRECT the ODS to activate the EPS for BFN.
Standard:
NA SAT UNSAT N/A COMMENTS:
Admin RO A4 PAGE 6
OF 7
Performance Step 5:
Critical Not Critical X 1.5 WHEN the EPS FAILS to operate either locally or by the ODS THEN exit this step and re-enter this Appendix at Step 2.0 Otherwise continue in this procedure.
Standard:
NA SAT UNSAT N/A COMMENTS:_________________________
Performance Step 6:
Critical X Not Critical 1.6. MONITOR the Paging System Terminal Display NOTE Monitor ERO positions through OSC Document Control. Positions below OSC Document Control are courtesy pages and are not subject to call-out requirements.
1.6.1 IF A NO response is observed, OR The position being paged has not responded promptly or within approximately 20 minutes, THEN UTILIZE the Weekly Duty List and attempt to contact the position representative with available information. (No Fitness for Duty question is required.)
Standard:
Operator determines that the TSC TAT RX ENGiNEER has not responded within 20 minutes. Operator utilizes the weekly duty list and calls the TSC TAT RX Engineer; NO answer by TSC TAT RX Engineer, Operator will determine he must call alternate position from the Call-Out List.
SAT UNSAT N/A COMMENTS:
Driver:
When called as the TSC TAT RX Engineer do not answer the phone to force Operator to utilize Call-Out list.
Admin RO A4 PAGE 7
OF 7
Performance Step 7:
Critical Not Critical 1.6.2 IF The individual cannot be reached utilizing the Weekly Duty List, THEN UTILIZE the Call-Out List and attempt to contact an alternate position representative. (Fitness for Duty question is required when utilizing the Call-Out List.)
Standard:
OPERATOR utilizes the Call-Out List and contacts an alternate position representative, once contacted Operator asks ifthe contacted alternate position representative is Fit For Duty SAT UNSAT N/A COMMENTS:
Driver:
When called as the alternate, answer the phone and allow Operator to call you in for emergency duty. Only respond to the questions you are asked do NOT volunteer any information; When asked, you are available and you are FIT FOR DUTY.
I CUE:
Another operator wifi perform the remaining actions END OF TASK STOP TIME
TODAY PAGING SYSTEM STATUS DISPLAY Start Time: 21 MIN AGO NOW Browns Ferry Nuclear Plant Page 1 of 4 POSITION PAGER PAGE
RESPONSE
NUMBER TIME TIME CONFIRMED SED STONE 10473 (01) 09:29 09:31 YES TAM THOMAS 30364 (01) 09:29 09:31 YES TSC TAT RX ENGR 60959 (01) 09:29 TSCTATICE 30361 (01) 09:29 09:31 YES TSCTATNSSS 40232 (01) 09:29 09:31 YES TSCTATBOP 90323 (01) 09:29 09:31 YES TSC TATL THOMPSON 90485 (01) 09:30 09:32 YES TSC RAD MGR HALL 70454 (01) 09:30 09:32 YES TSC CHEM NIGR BLACK 40842 (01) 09:30 09:32 YES TSC OPS MGR SELLS 15751 (01) 09:30 09:32 YES TSC OPS SPEC RICE 60252 (01) 09:30 09:31 YES TSC NUC SEC SMITH 70692 (01) 09:30 09:33 YES WESTINGHOUSEWELLS 20700 (01) 09:30 09:33 YES TSC NRCC LUCAS 90944 (01) 09:30 09:33 YES ABORT NEXT PAGE PREVIOUS PAGE
TODAY PAGING SYSTEM STATUS DISPLAY Start Time: 21 MIN AGO NOW Browns Ferry Nuclear Plant Page 2 of 4 POST N
PAGER PAGE
RESPONSE
C N
I 10 NUMBER TIME TIME 0
FIRMED TSC EP MGR GRAY 30379 (01) 09:30 09:33 YES SVPCARTER 40127 (01) 09:30 09:33 YES OSC COMM SHARP 70670 (01) 09:30 09:33 YES TSC LOGWRITERWHITE 10163 (01) 09:30 09:32 YES OSC EPCWILLIAMS 90470 (01) 09:30 09:32 YES OSC ASST. MGR.
MAY 30950 (01) 09:30 09:33 YES OSC ASST MGR BLACK 30560 (01) 09:30 09:32 YES OSC MGRCUNNINGHAM 90255 (01) 09:30 09:33 YES OSC RAD SUPV WEST 90469 (01) 09:30 09:31 YES OSC MM NELSON 90325 (01) 09:30 09:33 YES OSC MM NIXON 90306 (01) 09:30 09:31 YES OSC EM HECK 90265 (01) 09:30 09:33 YES OSC EM HENLEY 30821 (01) 09:30 09:33 YES OSC IM CORDELL 90347 (01) 09:30 09:30 YES ABORT NEXT PAGE PREVIOUS PAGE
TODAY PAGING SYSTEM STATUS DISPLAY Start Time: 21 MIN AGO NOW Browns Ferry Nuclear Plant Page 3 of 4 POSITION PAGER PAGE
RESPONSE
C N
NUMBER TIME TIME 0
FIRMED OSC 1MB ARNOLD 90348 (01) 09:30 09:32 YES OSC PPM COLEMAN 90555 (01) 09:30 09:33 YES OSC NUC SEC SHIFT LT.
90284 (01) 09:30 09:31 YES OSC SAFETY MILLER 40059 (01) 09:30 09:31 YES OSC SAFETY WALKER 70485 (01) 09:30 09:32 YES OSC FIRE OPS RUSSELL 90478 (01) 09:30 09:33 YES TSC CLERK DOLITTLE 40209 (01) 09:30 09:32 YES tsc clerk steve 90473 (01) 09:30 09:34 YES tsc clerk Jackie 40205 (01) 09:30 09:34 YES tscclerkdiane 60381 (01) 09:30 09:34 YES OSC OPS ADV MOSS 10319 (01) 09:30 09:34 YES MEDIA SPECIALIST 40891 (01) 09:30 09:34 YES NRC POWELL 11020 (01) 09:30 09:34 YES nrcBrenda 11023 (01) 09:30 09:34 YES ABORT NEXT PAGE PREVIOUS PAGE
TODAY PAGING SYSTEM STATUS DISPLAY Start Time: 21 MIN AGO NOW Browns Ferry Nuclear Plant Page 4 of 4 PAGER PAGE
RESPONSE
POSITION NUMBER TIME TIME CONFIRMED NRC HOWARD 11030 (01) 09:30 09:31 YES OSC CLERK SYKES 50779 (01) 09:30 09:33 YES OPS ADV TAT MCKEE 90143 (01) 09:30 09:32 YES OPSADVTATTURNER 30487 (01) 09:30 09:32 YES OPS ADV TAT PATTON 10802 (01) 09:30 09:34 YES OSC CLERK PAT 20608 (01) 09:30 09:34 YES osc mgr Robert 90663 (01) 09:30 09:31 YES ABORT NEXT PAGE PREVIOUS PAGE
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Page 1
Instructions:
Radiological Emergency Personnel Callout List Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
SITE EMERGENCY DIRECTOR (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASIC THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Contacted I
Name Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
- BONO, STEVEN M.
- HUGHES, DANIEL L.
KIr4BERLIN, JEFFREY A.
RASMUSSEN, MATTHEW Time Address Team ORANGE RED GREEN BLUE Work Phone (555) 555-3781 (555) 555-2555 (555) 555-6213 (555) 555-2555 Home Phone (555) 555-1149 (555) 555-6518 (555) 555-0969 (555) 555-0174 Pager 10177 11704 10181 19116 H
Radiological Emergency Personnel Callout List Page 2
Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OPERATIONS MANAGER (Contact 1
- BAKER, WILLIAM J.
- HAMMETT, MICKEY S.
- MORRISON, JEFFERY D.
- VAUGHN, CHRIS L.
GREEN BLUE ORANGE RED Work Phone (555) 555-3271 (555) 555-7616 (555) 555-7921 (555) 555-2213 Home Phone (555) 555-6340 (555) 555-4245 (555) 555-0360 (555) 555-7232 91445 95939 10889 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Team Address 11741 AL
Page 3
Instructions Radiological Emergency Personnel Callout List Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
CONTROL RM COMMUNICATOR (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
- BINKLEY, DONALD C.
JR
- GIBSON, MICHAEL
- RUBY, JORDEN
- THARPE, MICHAEL Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Address AL Team RED GREEN ORANGE BLUE Work Phone (555) 555-3959 (555) 555-2783 (555) 555-2783 (555) 555-3949 Home Phone (555) 555-6485 (555) 555-0655 (555) 555-6506 (555) 555-4048 30413 11829 15751 15750 AL AL AL Signature
Page 4
Instructions Radiological Emergency Personnel Callout List Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
TECHNICAL ASSESSMENT MGR (Contact 1
Name
- BRUCE, MICHAEL B.
- DONAHUE, PETE
- DURR, MICHAEL J.
- FREVOLD, ERIC J.
- KING, RONALD Team ORANGE RED ORANGE BLUE GREEN Work Phone (555) 555-3079 (555) 555-2660 (555) 555-2503 (555) 555-7826 (555) 555-2016 Home Phone (555) 555-5280 (555) 555-8003 (555) 555-5119 (555) 555-3218 (555) 555-5255 Pager 11845 11920 15433 10600 70942 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Address
cm Radiological Emergency Personnel Callout List Page 5
Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
RADCON MANAGER (Contact 1
- COLE, TONY ALLEN
- COWAN, STEVEN R.
- FERGUSON, JOE
- NORRIS, ROBERT BLUE RED ORANGE GREEN Work Phone (555) 555-2400 (555) 555-6262 (555) 555-2617 (555) 555-2490 Home Phone (555) 555-1570 (555) 555-2261 (555) 555-1843 (555) 555-0013 Pager It 95775 15336 11244 19184 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time I
Contacted Name Team Address AL
,AL
Page 6
Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
MAINTENANCE MANAGER (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE HOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If
- YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
- BROWN, STEVE
- FLOYD, MARK
- MCBAY, BLAKE
- REDING, RICHARD J.
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Team RED GREEN BLUE ORANGE Work Phone (555) 555-2647 (555) 555-3646 (555) 555-7799 (555) 555-6483 Home Phone (555) 555-8046 (555) 555-6495 (555) 555-1321 (555) 555-6919 Pager 15300 15090 20640 91347 Address AL
Page 7
Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC DIRECTOR (Contact 1
- FLOWERS, DAVID F.
GANDENBERGER, DONALD J.
- KELLEY, SCOTT
- KEMP, REGINALD A.
Li Team ORANGE RED BLUE GREEN Work Phone (555) 555-7400 (555) 555-3170 (555) 555-3160 (555) 555-2431 Home Phone (555) 555-1398 (555) 555-5861 (555) 555-1771 (555) 555-6419 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Address AL 95065 15681 40374 10107 AL AL AL Signature
Page 8
Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC ELECTRICAL SUPERVISOR (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Team Home Phone Address
- BAXTER, BEN
- CAMARGO, SUSAN M.
- HARROLD, STEVEN
- POWERS, JAMES J.
- PULLER, EDGAR L.
- SPEARS, STEPHEN
- WALTON, M.
SHAWN
- WENDELL, RODNEY Work Phone (555) 555-6015 (555) 555-7983 (555) 555-7735 (555) 555-7735 (555) 555-7735 (555) 555-7735 (555) 555-3265 (555) 555-7735 (555)
(555)
(555)
(555)
(555)
(555)
(555)
(555) 555-6068 555-6187 555-0772 555-7343 555-0685 555-1744 555-5094 555-0085 Pager 91349 92623 15099 15022 10977 15098 95300 95531 AL
,AL AL AL AL AL AL AL Signature
Page 9
Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC I/C SUPERVISOR (Contact 1
- WEAVER, DWIGHT A.
- BURCHAM, JOSHUA J.
- CRUNK, WILLIAM T.
- JOHNSON, DAVID L.
- JOHNSON, MICHEAL P.
- SOLLEY, JACKIE L.
TOMLINSON, MARK E.
BLUE ORANGE ORANGE GREEN RED BLUE RED Work Phone (555) 555-3253 (555) 555-2039 (555) 555-6204 (555) 555-2039 (555) 555-3642 (555) 555-2422 (555) 555-3638 Home Phone (555) 555-9115 (555) 555-6967 (555) 555-2766 (555) 555-0823 (555) 555-9188 (555) 555-4404 (555) 555-8821 Pager It 60824 15711 60593 14962 11772 30850 14680 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time I
Contacted Name Team Address AL
Page 10 Instructions:
Radiological Emergency Personnel Callout List Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X
by his/her name and try another person.
OSC MECHAWICAL SUPERVISOR (Contact 1
- BORDER, JUDI B.
- ATCHLEY, DELMER D.
- MERRINER, SCOTT E.
- VIDALIER, KELLY J.
Team BLUE RED ORANGE GREEN Work Phone (555) 555-3080 (555) 555-7504 (555) 555-6970 (555) 555-2403 Home Phone (555) 555-6235 (555) 555-2376 (555) 555-2806 (555) 555-6654 Pager 90721 95467 14408 15091 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time I
Contacted Name Address AL
Page 11 Instructions Radiological Emergency Personnel Callout List Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC RADCON MANAGER (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Team Home Phone CAGLE-JAUDON, TERRI
- CARSON, DONNA D.
HAr4ILTON, ANTHONY T.
- HENRY, KENNETH
- JOHNSON, DAVID S
- KELLER, JOE E.
ON SHIFT RADCON SUPV.
- SCONE, GEORGE E.
- WEBB, ROBERT G.
Work Phone (555) 555-6186 (555) 555-7179 (555) 555-2576 (555) 555-3063 (555) 555-3104 (555) 555-3104 (555) 555-3104 (555) 555-3793 (555) 555-3104 (555)
(555)
(555)
(555)
(555)
(555)
Address 555-9762 555-9076 555-3031 555-5651 555-9938 555-7339 Pager 96007 12407 95641 11773 95779 12412 90500 AL
,AL AL AL AL TN (555) 555-3586 (555) 555-9484 15334 AL 95773 AL Signature
Radiological Emergency Personnel Callout List Page 12 Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
TECHNICAL ASSESSOR #1 (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time I
Contacted Team Address Name DR LA GARZA, RODRIGO
- HAYES, WILLIAM R.
- KING, JESSE V.
- LONG, TELISSA K.
- MARSH, DAVID
- STORCH, ROBERT H.
WILLIAMSON, BILL T.
Work Phone (555) 555-4704 (555) 555-4743 (555) 555-4751 (555) 555-4748 (555) 555-4782 (555) 555-4740 (555) 555-4725 Home Phone (555) 555-1570 (555) 555-4938 (555) 555-2720 (555) 5553593 (555) 555-4664 (555) 555-9463 (555) 555-5007 Pager 70935 10218 70565 90228 15016 13427 10292 AL AL AL AL AL AL AL Signature
Page 13 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC ELECTRICAL ENGINEER (Contact 1
- BELCHER, AMOS H.
- BOUSLOG, WILLIAM
- HOANG, WILL
- SAMPSON, JAMES R.
(555) 555-3169 (555) 555-7589 (555) 555-3140 (555) 555-7420 Home Phone (555) 555-2113 (555) 555-9432 (555) 555-1158 (555) 555-8250 Pager 40962 15213 14338 10178 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Team Work Phone BLUE GREEN RED ORANGE Address AL AL AL AL Signature
(Th n
Page 14 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC MECHANICAL ENGINEER (Contact 1
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Team Work Phone Home Phone Address Pager 60275 14213 60826 11980 95555 70504 20015 14891 11756
- CURTHS, DAVID W.
BLUE (555) 555-7955 (555) 555-4488 AL
- KIRBY, EDWARD E.
ORANGE (555) 555-3168 (555) 555-2706 AL
- P4INGUS, III THOMAS M.
RED (555) 555-7315 (555) 555-1665 AL
- ELLETT, MICHAEL ORANGE (555) 555-7734 (555) 555-2997 AL
- GRONEK, JAMES W.
(555) 555-6903 (555) 555-8046 AL HENDERSON, MICHAEL GREEN (555) 555-7494 (555) 555-1392 AL
- INGRAM, SANDY RED (555) 555-2685 (555) 555-9461 AL
- ROBBINS, LUKE GREEN (555) 555-3149 (555) 555-3180 AL
- STAFFORD, LARRY T.
BLUE (555) 555-5553 (555) 555-6741 AL MESSAGE:
We have a(an) classification at Nuclear Plant.
Please report to your emergency station immediately to fill your assigned position.
ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Signature
Page 15 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
CHEMISTRY MAWAGER (Contact 1
- BLACK, JOHNNIE S.
- CAMP, H.
ARNIE
- FENTON, JEFFERY D.
- HAMILTON, BRYAN W.
UNDERWOOD, JOHN W.
Team RED GREEN BLUE ORANGE Work Phone (555) 555-2036 (555) 555-2640 (555) 555-2974 (555) 555-2682 (555) 555-3707 Home Phone (555) 555-1473 (555) 555-5108 (555) 555-5810 (555) 555-1565 (555) 555-2887 Pager 20103 20107 20124 60731 11162 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If
- YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Address
,AL
Radiological Emergency Personnel Callout List Page 16 Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
SITE VICE PRESIDENT (Contact 1
- CHASE, PHIL L
MALINOWSKI, DAVID A.
- MARLOW, THOMAS A.
- MORRIS, JEFF
- PIERCE, BILLY W.
Team BLUE ORANGE GREEN RED RED Work Phone (555) 555-3035 (555) 555-3439 (555) 555-3078 (555) 555-3957 (555) 555-3607 Home Phone (555) 555-5967 (555) 555-6658 (555) 555-6473 (555) 555-9609 (555) 555-6944 14574 60885 14043 15943 55584 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthonzed personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Address AL
Page 17 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OPERATIONS SPECIALIST (Contact 1
Name
- BARKER, JEFFREY S.
- BENNETT, JOSEPH G.
ROBERTSON, DONALD T.
- STOVALL, MICHAEL G.
BLUE RED ORANGE GREEN Work Phone (555) 555-7953 (555) 555-7545 (555) 555-7971 (555) 555-3227 Home Phone (555) 555-5559 (555) 555-6083 (555) 555-3502 (555) 555-2365 30547 13487 94801 13146 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Team It Address AL AL AL Signature
Im Radiological Emergency Personnel Callout List n
Page 18 Instructions:
Do not notify persons noted with an
(*)
for more than one position. Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
TECH ASSESSMENT TM LEADER (Contact 1
- FORD, DAVID K.
- GROOM, KEVIN L.
- KECK, JANES N.
- NILSEN, FREDERICK J.
Team ORANGE BLUE RED GREEN Work Phone (555) 555-2097 (555) 555-7491 (555) 555-4750 (555) 555-2958 Home Phone (555) 555-8347 (555) 555-2122 (555) 555-3128 (555) 555-2093 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time I
Pager Contacted Name Address AL 11776 90241 10255 10244 AL AL AL Signature
Page 19 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
ASST.
RADCON MA1TAGER (Contact 1
- COLE, AIMEE
- CREAMER, CHARLES E.
- DUNCAN, JOSHUA A.
- HARRIS, JIM
- PETE, WENDELL F.
- SCHMEHL, RICHARD S.
GREEN ORANGE BLUE Work Phone (555) 555-6276 (555) 555-2983 (555) 555-2996 (555) 555-2968 (555) 555-6364 (555) 555-2007 Home Phone (555) 555-1570 (555) 555-8021 (555) 555-4733 (555) 555-1186 (555) 555-1141 (555) 555-4617 Pager 95778 30053 14508 55585 96012 30213 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Team Address RED AL AL
Page 20 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
TSC COMMUNICATOR (Contact 1
- BURTON, JAMES W.
- JACKSON, JASON
- COMEENS, JENNIFER
- FOWLER, LAKESHA M.
- LEONARD, QUINN
- MITCHELL, CHANNING
- PEYTON, ANDREW Team BLUE GREEN ORANGE GREEN BLUE ORANGE RED Work Phone (555) 555-7938 (555) 555-7666 (555) 555-7327 (555) 555-3089 (555) 555-7320 (555) 555-7754 (555) 555-2474 Home Phone (555) 555-8772 (555) 555-6592 (555) 555-4285 (555) 555-8580 (555) 555-9979 (555) 555-8796 (555) 555-9935 Pager
[
10599 10133 14889 14888 20083 15159 10028 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Address
,AL AL AL AL AL AL AL Signature
Page 21 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
TECHNICAL ASSESSOR #2 (Contact 1
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Team Work Phone Home Phone Pager 708 53 11780 10504 12549 40936 15921 95921 15920
- DOLLAR, CHARLES K.
ORANGE (555) 555-3141 (555) 555-1387 AL JONES III, W.
CASEY BLUE (555) 555-7388 (555) 555-5031 AL
- MOORE, SAMUEL W.
GREEN (555) 555-7521 (555) 555-2197 AL
- BAILES, CHARLES RED (555) 555-7651 (555) 555-3454 AL
- MOXLEY, ROBERT RED (555) 555-2754 (555) 555-9787 AL
- OATES, JANECZKA BLUE (555) 555-7623 (555) 555-6170 AL REISCHMAN, CHRIS GREEN (555) 555-8452 (555) 555-2244 AL
- WILSON, CHRIS ORANGE (555) 555-6070 (555) 555-7960 AL MESSAGE:
We have a(an) classification at Nuclear Plant.
Please report to your emergency station immediately to fill your assigned position.
ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Address Signature
Page 22 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
EP MANAGER (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Name
- FELTMAN, ANTHONY H.
- COLEMAN, ROB L.
- TIDWELL, BRADLEY F.
- WALDREP, JOHN R.
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time I
Contacted Address AL Team ORANGE BLUE RED GREEN Work Phone (555) 555-3666 (555) 555-3958 (555) 555-3108 (555) 555-2038 Home Phone (555) 555-5062 (555) 555-4490 (555) 555-6792 (555) 555-0296 Pager It 90759 55581 11934 60561
,AL
Page 23 Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
NUCLEAR SECURITY MAI%TAGER (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If
- YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Instructions fl..
Radiological Emergency Personnel Callout List Note; Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Team Home Phone Address Work Phone
- BRYANT, GRADY L.
555) 555-3150 (555) 555-1018 AL CHURCHWELL, SHANNON D.
(555) 555-3479 (555) 555-6907 30105 AL ELLENBURG, GREGORY A.
(555) 555-4955 (555) 555-2064 91870 AL
- EMBERY, DONALD L.
(555) 555-3692 (555) 555-9571 AL
- ISBELL, JUSTIN T.
(555) 555-2219 (555) 555-9892 AL
- NEWTON, JAMES R.
(555) 555-3150 (555) 555-8844 10214 AL ON SHIFT SECURITY SUPV.
(555) 555-2219 (555) 555-2219 10214
- PARKER, PATRICK L.
(555) 555-3028 (555) 555-1030 60812 AL
- SLOAN, DAVID C.
(555) 555-2219 (555) 555-4628 AL
- ULTZ, RONALD B.
(555) 555-2219 (555) 555-1389 AL Signature
Page 24 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
SITE ENGINEERING MANAGER (Contact 1
- BOONE, MICHAEL J.
- COLVIN, JOHN E.
- LOVVORN, SHANNON
- SAMARAS, STEPHEN
- WEBSTER, DAN YARBROUGH, J.
ANGEL Team GREEN ORANGE BLUE BLUE RED GREEN Work Phone (555) 555-7402 (555) 555-2427 (555) 555-7618 (555) 555-7509 (555) 555-7902 (555) 555-2524 Home Phone (555) 555-2851 (555) 555-2316 (555) 555-6939 (555) 555-4060 (555) 555-5265 (555) 555-3042 Pager 95013 15131 12413 30461 95809 11723 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If
- YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Address AL
Page 25 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
ASSISTAZTT OSC DIRECTOR (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
- HARRIS, PAUL PATTERSON, THOMAS B.
- SKARP, ROGER T.
- sTARBucK, WILLIAN C.
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Address AL Team ORANGE RED BLUE GREEN Work Phone (555) 555-3195 (555) 555-4841 (555) 555-6974 (555) 555-2039 Home Phone (555) 555-2232 (555) 555-1368 (555) 555-8340 (555) 555-7720 90414 15149 15314 15224 AL AL AL Signature
Page 26 Instructions:
Radiological Emergency Personnel Callout List Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC TEAM MAI4IAGER (Contact 1
Home (555)
(555)
(555)
(555)
(555)
(555)
Phone 555-9973 555-1025 555-5077 555-6766 555-0035 555-7136 Pager It 96 03 2 96037 30087 96031 40378 70562 AL AL AL AL AL AL MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time I
Contacted Name Team Address
- QUINN, BERNARD
- CABLE, JEFFREY C.
- HOGAN, STEVE
- HUNTER, DOUGLAS E.
LEINNEWEBER, VERNON E.
- SHULTS, TRAVIS Work Phone (555) 555-7137 (555) 555-6074 (555) 555-7783 (555) 555-6496 (555) 555-6211 (555) 555-2040 Signature
Radiological Emergency Personnel Callout List Page 27 Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
FIRE PROTECTION MANAGER (Contact 1
- BRYANT, MICHAEL R.
- SMITH, HAYDEN
- STEPHENS, THOMAS B.
JR Team GREEN RED ORANGE Work Phone (555) 555-2971 (555) 555-2468 (555) 555-2555 (555) 555-5856 (555) 555-0619 (555) 555-2555 10297 60274 10923 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Time Contacted Name Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is Drohibited by the Privacy Act and is unishableby law Pager Home Phone Address AL AL
,AL Signature
Page 28 Instructions Radiological Emergency Personnel Callout List Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC CHEMISTRY MANAGER (Contact 1
Name
- PITCOCK, ROBERT E.
- LOUALLEN, BARRY E.
OLIVER-BELCHER, TRACI
- REYNOLDS, ALBERT
- ROBINSON, DOUGLAS C.
Work Phone 555) 555-7442 (555) 555-2959 (555) 555-7129 (555) 555-3242 (555) 555-2913 Home Phone (555) 555-5095 (555) 555-4045 (555) 555-2113 (555) 555-9040 (555) 555-0123 Pager 20117 10868 90392 11326 10888 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If
- YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Signature Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Team Address
Page 29 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC OPERATIONS MA1TAGER (Contact 1
- BRANAM, DANA L.
- TAYLOR, THOMAS P.
- BOHANAN, TODD A.
- BOLAND, TIMOTHY D.
- HOLLIDAY, JOHN E.
- HOLM, RANDALL 0.
- SCOTT, TIMOTHY L.
RED BLUE GREEN ORANGE RED BLUE Work Phone (555) 555-2927 (555) 555-2171 (555) 555-7972 (555) 555-7109 (555) 555-2489 (555) 555-3002 (555) 555-2190 Home Phone (555) 555-8848 (555) 555-8559 (555) 555-3874 (555) 555-5321 (555) 555-8984 (555) 555-2261 (555) 555-4328 Pager 14765 60088 15444 14155 15563 12696 15237 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Team Address AL AL AL AL
Radiological Emergency Personnel Callout List Page 30 Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
TSC TAT RX ENGINEER (Contact 1
- HIPPS, ANTHONY R.
- STEVENS, LEONARD G.
- MERGY, STEPHEN D.
- WEATHER, WILLIAM C.
Team BLUE GREEN RED ORANGE Work Phone (555) 555-2389 (555) 555-2389 (555) 555-2389 (555) 555-2389 Home Phone (555) 555-5182 (555) 555-6217 (555) 555-1067 (555) 555-6962 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Address AL 55550 55578 55528 55501 AL AL AL Signature
Page 31 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
NRC COORDINATOR (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
- AUSTIN, STEVE W.
- OLIVER, MICHAEL W.
- BATES, RICHARD ERIC
- EMENS, JAMES E.
JR Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Address 60737 AL Team ORANGE RED GREEN BLUE Work Phone (555) 555-2070 (555) 555-7874 (555) 555-7180 (555) 555-2636 Home Phone (555) 555-9567 (555) 555-2028 (555) 555-4314 (555) 555-4669 14110 15257 10980 AL AL
,AL Signature
Radiological Emergency Personnel Callout List Page 32 Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
TSC STATUSBOARD WRITER (Contact 1
- SKINNER, KEITH
- WETZEL, STEWART A.
CRITTENDEN, GERALD L.
- DISSPAIN, JAIME L.
- GARNER, FRANKIE
- JACKSON, DARYL
- KENT, JAMES A.
Team GREEN RED ORANGE BLUE RED ORANGE 14111 90591 15136 AL 14890 91348 14861 13077 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Address AL Work Phone (555) 555-2649 (555) 555-7556 (555) 555-7886 (555) 555-7403 (555) 555-7681 (555) 555-3604 (555) 555-3177 Home Phone (555) 555-2009 (555) 555-9919 (555) 555-4693 (555) 555-0555 (555) 555-1135 (555) 555-4213 (555) 555-0079 AL
Radiological Emergency Personnel Callout List Page 33 Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC STATUSBOARD WRITER #1 (Contact 1
Name MCCORMACK, JOHN C.
SCHIAVONE, VICTOR D.
- VANDIVER, LESLIE B.
- WILLIAMS, JONATHAN C.
- HARVEY, KELLI S.
- LACASSE, JOHN T
- MOORE, JOHN T.
Team RED BLUE ORANGE BLUE GREEN RED GREEN Work Phone (555) 555-7582 (555) 555-2607 (555) 555-7555 (555) 555-3250 (555) 555-7576 (555) 555-7235 (555) 555-3052 Home Phone (555) 555-1286 (555) 555-8681 (555) 555-5014 (555) 555-5399 (555) 555-3591 (555) 555-1213 (555) 555-7369 MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If
- YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Address Pager 10262 10555 11872 10182 20028 95584 12681 AL
Page 34 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC STATUSBOARD WRITER #2 (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
- CURRY, DAVID A.
- GENTRY, KERRY L.
- f4ARSTON, MICHAEL R.
- WEBB, RANDALL Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Address AL Team GREEN ORANGE BLUE RED Work Phone (555) 555-3147 (555) 555-7593 (555) 555-3163 (555) 555-3127 Home Phone (555) 555-5021 (555) 555-1594 (555) 555-2064 (555) 555-9322 90437 11903 70585 10940 AL TN AL Signature
Page 35 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
MATERIALS COORDINATOR (Contact 1
Home (555)
(555)
(555)
(555)
(555)
(555)
(555)
(555)
(555)
(555)
(555)
Phone 555-0307 555-5744 555-0042 555-0572 555-4426 555-2886 555-9058 555-9173 555-6549 555-7944 555-8347 Pager 70806 14771 90954 90252 12768 20201 14415 93530 15717 12660 70447 AL AL AL AL AL AL AL AL AL AL AL MESSAGE:
We have a(an) classification at station immediately to fill your assigned position.
ASK THE FOLLOWING QUESTIONS:
Nuclear Plant.
Please report to your emergency 1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time I
Contacted Name Team Address
- BENTLEY, GREG BOWMAN JEFFREY L.
- FORD, VERNARD
- GOOCH, TIMOTHY L.
- HOGAN, DONAHUE
- HUDSON, B.
AUTRY
- IRONS, ARNELL
- PUTMAN, KEITH
- ROBINSON, KIM
- SHElL, TIMOTHY M.
- WILLIAMS, CAROLYN R.
Work Phone 555) 555-3340 (555) 555-4551 (555) 555-7034 (555) 555-3868 (555) 555-4868 (555) 555-2889 (555) 555-6939 (555) 555-4673 (555) 555-7085 (555) 555-4809 (555) 555-7401 Signature
Radiological Emergency Personnel Callout List Page 36 Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC STAGING AREA MANAGER (Contact 1
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Team Address
(
AL BLENKINSOPP, JOHN
- BRYAN, JAMEY E.
- CLAUNCH, DONNIE R.
- HATTON, BYRON L.
- HILL, BILLY
- PEDEN, DAVID L.
RED GREEN ORANGE BLUE Work Phone 555) 555-7204 (555) 555-7634 (555) 555-2677 (555) 555-2769 (555) 555-6171 (555) 555-4949 Home Phone (555) 555-8280 (555) 555-4405 (555) 555-5655 (555) 555-6587 (555) 555-7333 (555) 555-6041 95562 94997 AL 40939 AL 15148 16059 70855 AL AL AL Signature
Page 37 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC DOCUMENT CONTROL (Contact 1
Work Phone (555) 555-4654 (555) 555-3809 (555) 555-2733 (555) 555-2014 Home Phone (555) 555-0083 (555) 555-6733 (555) 555-1818 (555) 555-9669 Pager 40132 70841 11968 AL 14493 AL MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
- BURT, SUSAN A.
- MCBAY, MARTHA A.
- CAMPBELL, CHRISTI L.
- CLARK, COURTNEY Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Team Address
Radiological Emergency Personnel Callout List Page 38 Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
TSC CLERK (Contact 3
Name
- ATKINS, CHRISTY H.
- BRIGGS, CASEY L.
- CARTER, MARY
- CURTIS, VIRGINIA A.
- MABRY, DARLENE T.
- WILSON, DENA D.
- WORD, KASEY Team GREEN RED BLUE BLUE GREEN RED ORANGE Work Phone (555) 555-7723 (555) 555-3095 (555) 555-4860 (555) 555-3643 (555) 555-2029 (555) 555-3220 (555) 555-2190 Home Phone (555) 555-9659 (555) 555-8825 (555) 555-6220 (555) 555-3271 (555) 555-5753 (555) 555-5610 (555) 555-0733
,AL
We have a(an) classification at station immediately to fill your assigned position.
Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If
- YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted It Address 60651 95010 15037 14199 Signature
Radiological Emergency Personnel Callout List Page 39 Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided.
If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC CLERK (Contact 3
MESSAGE:
We have a(an) classification at station immediately to fill your assigned position Nuclear Plant.
Please report to your emergency ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
- GRIFFIS, AMY D.
- HERBSTER, KERRI S.
- SNEED, CELENA
- THOMAS, WANDA Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Pager Contacted Name Address Team GREEN RED BLUE ORANGE Work Phone (555) 555-3712 (555) 555-6369 (555) 555-2190 (555) 555-2841 Home Phone (555) 555-0842 (555) 555-7213 (555) 555-2669 (555) 555-7848 15211 AL
Page 40 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
OSC PLANNERS (ContaCt 2
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Team Work Phone Home Phone Address Pager 146 75 14358 60279 15598 60648
- BERRY, DARRIN (555) 555-2090 (555) 555-0459 AL
- BOYD, VICTOR A.
(555) 555-7814 (555) 555-6038 AL
- BROWN, K.
B.
(555) 555-2421 (555) 555-5188 AL
- CARRIN, WILLIAM V.
(555) 555-7404 (555) 555-1113 AL
- CHORNEY, ANTHONY H.
(555) 555-3219 (555) 555-3675 AL
- CRAFT, CHRIS (555) 555-3259 (555) 555-9571 AL
- EDMONSON, PAMELA (555) 555-7987 (555) 555-0176 AL
- FOWLER, BRIAN (555) 555-7247 (555) 555-3102 15599 AL
- HUGHES, NORRIS Q.
(555) 555-7685 (555) 555-0469 90497 AL
- JOHNSON, DEBRA C.
(555) 555-2499 (555) 555-1937 95645 AL
- JOHNSON, MICHAEL (555) 555-5552 (555) 555-6754 15601 AL
- JONES, GREGORY R.
(555) 555-7471 (555) 555-2273 15600 AL
- PRICE, TIMOTHY R
(555) 555-2415 (555) 555-5199 10799 TN RICHARDSON, ASHLEY A.
(555) 555-3067 (555) 555-2391 40525 AL
- RILEY, DEXTER E.
(555) 555-3263 (555) 555-8538 15273 AL
- SHERRILL, BRYAN L.
(555) 555-7765 (555) 555-4992 30229 AL
- SOLLEY, JIMMY (555) 555-6034 (555) 555-6806 14678 AL
- SPENCER, EDWARD (555) 555-7448 (555) 555-9633 70584 AL
- STRINGER, LEONARD (555) 555-7922 (555) 555-7406 15741 AL VAN BUREN, BRIAN E
(555) 555-6176 (555) 555-5919 14679 AL
- VANDIVER, JERRY W.
(555) 555-7636 (555) 555-6743 60152 AL
- WEEKS, DEBORAH K.
(555) 555-6426 (555) 555-8468 95772 AL
- WILSON, STEPHANIE (555) 555-7933 (555) 555-6479 14430 AL MESSAGE:
We have a(an) classification at Nuclear Plant.
Please report to your emergency station immediately to fill your assigned position.
Page 41 kSK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Signature
Page 42 Radiological Emergency Personnel Callout List Instructions:
Do not notify persons noted with an
(*)
for more than one position.
Contact as many people in each group as noted.
When an individual is contacted, enter the time contacted next to his/her name in the space provided. If an individual cannot be contacted by telephone or pager, place an X by his/her name and try another person.
SHIFT M?IAGER / SED (Contact 1
Note:
Disclosure of home telephone numbers to unauthorized personnel or misuse of private information is prohibited by the Privacy Act and is punishable by law.
Time Contacted Name Team Work Phone Home Phone Address Pager 30109 11810 91445 30981 10181 12379 95939 95935 19116 70567 10889 60280
- CAMPBELL, DENNY W.
(555) 555-3478 (555) 555-9537 AL HAKENEWERTH, DOUGLAS G.
(555) 555-2213 (555) 555-4992 AL
- HAMMETT, MICKEY S.
BLUE (555) 555-7616 (555) 555-4245 AL
- HUNTER, MICHAEL D.
(555) 555-2213 (555) 555-1683 AL KIMBERLIN, JEFFREY A.
GREEN (555) 555-6213 (555) 555-0969 AL
- MCNUTT, BRIAN K.
(555) 555-2213 (555) 555-1951 AL
- MORRISON, JEFFERY D.
ORANGE (555) 555-7921 (555) 555-0360 AL
- NASH, MICAH T.
(555) 555-2213 (555) 555-4497 AL RASMUSSEN, MATTHEW BLUE (555) 555-2555 (555) 555-0174 AL
- STOWE, RONALD H.
(555) 555-2213 (555) 555-9623 AL
- VAUGHN, CHRIS L.
RED (555) 555-2213 (555) 555-7232 AL
- WHITE, KELLY J.
(555) 555-2213 (555) 555-9321 AL MESSAGE:
We have a(an) classification at Nuclear Plant.
Please report to your emergency station immediately to fill your assigned position.
ASK THE FOLLOWING QUESTIONS:
1)
Have you consumed alcohol within the past five hours?
YES or NO (If
- YES, instruct not to report and call next name.)
2)
Are you fit for duty?
YES or NO (If NO, instruct not to report and call next name.)
Signature
Admin SRO A4 PAGE 1
OF 5
OPERATOR:
SRO DATE:
JPM NUMBER:
Admin SRO A4 TASK NUMBER:
S-000-EM-21 (SRO ONLY)
TITLE:
Classify the event per REP (Fuel Damage with RCIC Steam Leak)
K/A NUMBER:
2.4.4 1 KIA RATING: SRO 4.6 TASK STANDARD: The event is classified as a AlertSite Area Emergency, EAL Designator 2.3-S-I-A OR 1.3-A and the Initial Notification appendix is completed with the correct information. Event is classified within 15 minutes and Initial Notification is completed within 15 minutes of classification with correct Protective Action Recommendation.
LOCATION OF PERFORMANCE: Simulator or Classroom REFERENCES/PROCEDURES NEEDED:
VALIDATION TIME: 30 minutes MAX. TIME ALLOWED: 15 minutes to classify and 15 minutes to notify PERFORMANCE TIME:
COMMENTS:
4 te Highec-Iaw4 ertvwj t%.4-M-E4-T LreS avt RCi C 7 L - 2..
s j..e-JPW.
Additional comment sheets attached? YES NO RESULTS:
SATISFACTORY UNSATISFACTORY SIGNATURE:____________
DATE:
EXAMTh.ER
INITIAL CONDITIONS: You are the SHIFT MANAGER. Unit 2 was operating at 80% power performing a Control Rod Pattern Adjustment. During the Control Rod Pattern Adjustment, Control Rod 3 8-23 dropped several notches. Unit shutdown was in progress when a RCIC steam leak developed.
A Reactor SCRAM was inserted and the following conditions exist:
The TSC, OSC and CECC are not staffed at this time.
Reactor Level 10 inches and slowly rising Reactor Pressure 950 psig and stable DW Pressure 1.35 psig and stable DW Temperature 135°F and stable DW Oxygen 2.9% and slowly rising DW Hydrogen 2.4% and slowly rising Chemistry Sample 310 iCi/gm (Dose Equivalent 1-131)
DW Radiation 2-RM-90-272A is reading 2900 R/Hr 2-RM-90-273A is reading 1300 R/Hr PCIS Isolation Group 5 Is NOT complete, RCIC Valves 71-2 and 71-3 failed to auto close, RCIC Valve 71-2 was closed with Control Room operator action.
RCIC Area TE-71-41A indicates 195°F RCIC Room 90-26A 600 mremlhr Wind Speed 10 mph Wind Direction 200° Projected TEDE at site boundary
<1 REM Projected Thyroid CDE at site boundary
<5 REM INITIATING CUE: Identify the HIGHEST REQUIRED emergency classification, and complete the associated initial notification form. Raise your hand immediately once you have classified the event, and the examiner will then provide you with the EPIP youve chosen so you can begin completing the initial notification form.
JPM is Time Critical
Admin SRO A4 PAGE 3
OF 5
Classroom INITIAL CONDITIONS: You are the SHIFT MANAGER. Unit 2 was operating at 80% power performing a Control Rod Pattern Adjustment. During the Control Rod Pattern Adjustment, Control Rod 3 8-23 dropped several notches. Unit shutdown was in progress when a RCIC steam leak developed.
A Reactor SCRAM was inserted and the following conditions exist:
The TSC, OSC and CECC are not staffed at this time.
Reactor Level 10 inches and slowly rising Reactor Pressure 950 psig and stable DW Pressure 1.35 psig and stable DW Temperature 135°F and stable DW Oxygen 2.9% and slowly rising DW Hydrogen 2.4% and slowly rising Chemistry Sample 310 jiCi/gm (Dose Equivalent 1-131)
DW Radiation 2-RM-90-272A is reading 2900 R/Hr 2-RM-90-273A is reading 1300 R/Hr PCIS Isolation Group 5 Is NOT complete, RCIC Valves 71-2 and 71-3 failed to auto close, RCIC Valve 71-2 was closed with Control Room operator action.
RCIC Area TE-71-41A indicates 195°F RCIC Room 90-26A 600 mrem!hr Wind Speed 10 mph Wind Direction 200° Projected TEDE at site boundary
<1 REM Projected Thyroid CDE at site boundary
<5 REM INITIATING CUE: Identify the HIGHEST REQUIRED emergency classification, and complete the associated initial notification form. Raise your hand immediately once you have classified the event, and the examiner will then provide you with the EPIP youve chosen so you can begin completing the initial notification form.
JPM is Time Critical
Admin SRO A4 PAGE 4
OF 5
START TIME____
Performance Step 1:
Critical X Not Critical Refers to EPIP 1 to classify emergency event.
Standard:
SHIFT MANAGER refers to EPIP land declares an Alert Site Area Emergency, EAL 2.3-S4-, based on Drywell Radiation reading greater than 2263 4on 2-RE-90-272A, OR 1.3-A, based on Iodine-13 1 coolant activity >300 CiIgm.
SAT_ UNSAT N/A COMMENTS:____________________________
TIME Classified
Admin SRO A4 PAGE 5
OF 5
START TIME____
Performance Step 2:
Critical X Not Critical Implements EPIP-4 Site Area Emergency Alert and completes Appendix A of EPIP 3.
Standard:
Shift Manager completes Appendix A of EPIP.4 within 15 minutes of event classification SAT_ UNSAT N/A COMMENTS:_____________________________
TIME Appendix A Complete Performance Step 3:
Critical X Not Critical Completes Appendix A of EPIP,4 Standard:
Following are Critical portions of Appendix A: Unit 2 is checked, EAL Designator 2.3-S-I-A OR 1.3-A, minor releases within federally approved limits is checked for Airborne/Liquid, Time and Date Event declared and PAR recommendation NONE is checked.
SAT UNSAT N/A COMMENTS:____________________________
END OF TASK