ML101650639
| ML101650639 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/07/2010 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| Download: ML101650639 (106) | |
Text
{{#Wiki_filter:FNP HLT-33 ADMIN Page 11 of 10 10 A.1.1.A Conduct of Operations ADMIN G2.1.40 - RO & SRO A.1.1.A A.1.1.A A. 1. l.A Verification of TITLE: Verification ofInitial Initial Conditions Prior to Core Alterations. PROGRAM APPLICABLE: SOT SOCT OL T .-lL OLT X LOCT____ LOCT_ _ ACCEPTABLE EVALUATION METHOD: ~ X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM ~ X CLASSROOM PROJECTED TIME: MIN 30 MN SIMULATOR IC NUMBER: SIMULATOR N/A ALTERNATE PATH TIME CRITICAL PRA_ _ PRA____ JPM DIRECTIONS:
- 1. This task is to be administered in a group, classroom setting with access to a variety of procedures (UOPs, STPs, SOPs, et al) available via the Exam Reference disk.
- 2. This task is designed to be performed with evaluation of pictures of the equipment from which operational information will be evaluated.
- 3. Due to the utilization of pictures, upon request, the status of the lights and switches may be clarified (See standards for the applicable light/switch).
- 4. Upon completion of elements 1-10, all candidates will be evaluated at the RO level.
- 5. FOR SRO candidates ONLY: after evaluation of elements 1-10, they will be provided a second Cue sheet (handout #2) and returned to the classroom to evaluate TS.
TASK STANDARD: Required for successful completion of this JPM: NOTE: Incorrect assessment of any step within the appendix, or entry into any non-applicable LCO would constitute a critical task failure.
- Assess all steps of UOP-4.1, Appendix 6, Verification of Initial Conditions Prior to Core Alterations and identify all, if any, core alt. initial conditions listed in UOP-4.1, Appendix 6 which are not satisfied.
* (For SRO ONLY): Based on the conditions identified list all TS CONDITIONS, REQUIRED ACTIONS and COMPLETION TIMES for LCOs not met, ifany. if any.
Examinee: Overall JPM Performance: Satisfactory 0E1 Unsatisfactory 0D Evaluator Comments (attach additional sheets if necessary) EXAMINER: EXAMINER: _________________ Developer H. Fitzwater 2/09/10 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLT-33 ADMIN FNPHLT-33ADMIN A.1.1.A A.1.1.A Page2oflO Page 2 of 10 CONDITIONS CONDITIONS When II tell tell you you to you are to begin, you to perform are to evaluate all or evaluate perform or all steps steps FNP-FNP-I-UOP-4.1, Appendix 6, 1 -UOP-4. 1, Appendix 6, Conditions Prior to Core Alterations. The conditions under which this task is to Verification of Initial Conditions performed are: be performed
- a. Core Offload was suspended 18 Core 18 hours ago.
- b. RCS temp is 100°F.
100°F.
- c. Time to boil is >2 hours.
- d. A Fuel shuffle in the Spent Fuel Pool is ongoing.
- e. Communications between the MCR and a System Operator acting as the Cavity Watch have 10 minutes ago.
been verified available 10
- f. concentration is 2450 ppm following an over boration performed last shift.
RCS boron concentration
- g. chemistry's request.
Rx Makeup water is being used to dilute the Reactor Cavity by chemistrys
- h. FNP1-STP-1 FNP-I-STP-18.4, andlor Refueling Integrity Verification and 8.4, Containment Midloop and/or Containment Closure, was completed yesterday at 1400.
i.1. CTMT Main Purge system is in operation. j.J. The equipment hatch and all containment air locks are currently closed.
- k. The Ctmt Evacuation alarm is sounding inside Containment.
- 1. The Audio Count Rate Channel is NOT producing any audible noises.
- m. Applicable equipment will be assessed using the provided photographs.
- n. FNP-I-UOP-4. 1, Appendix 6.
You have been directed to perform or evaluate all steps of FNP-1-UOP-4.1,
- o. Identify all initial conditions for core alterations listed in UOP-4.1, Appendix 6, which are not satisfied, if any.
INITIATING CUE: "You begin. You may begin." EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME
- 1. (STEP 2.1 & & 2.2) Checks correct version and 1) Determines step 2.1 & & 2.2 has S / U S/U conducted on appropriate unit. been completed. Utilizes WebTop and verifies unit from initial conditions
- 2. (STEP 3.1) Communications between MCR and 2) Determines step 3.1 has been S / U S/U the Reactor Cavity verified within one hour. completed. Utilizes initial conditions to verify task complete.
NOTE:* NOTE:
- Elements 3 through 5, 7 and 8 are performed by use of pictures. The pictures are sufficient to demonstrate light status and switch position, however IF light status or position is questioned, then the cues may be provided (see the standards column for the applicable light or switch).
HLT-33 ADMIN FNP HLT-33 A.1.1.A Page 33 of 10 10 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: STANDARDS: (CIRCLE)
- 3. (STEP 3.2.1) Verify N-3 1, Source Range NI, N-31, 3) Determines step 3.2.1 has been SS /I U detector operable. satisfied; Utilizes picture of N-ofN-31 and determines that the instrument is operable.
(reference SOP-39.0 section 4.1)
- a. Check N-3N-31I Instrument power on AND control a. lights are illuminated power on lights illuminated.
- b. Check switches aligned: b. Switches are in position:
- i. Level Trip i. Normal I.
ii.Operation Selector ii. Normal 11. iii.High Flux at shutdown iii. Ill. Normal
- c. Perform a channel check per STP-1.0 STP-1 .0 (SR STP-1 .0
- c. Acceptable per STP-1.0 3.9.2.1). allowances
- 4. (STEP 3.2.2)Verify 3.2.2) Verify N-32, Source Range NI, 4) Determines step 3.2.2 can not S I/ U S
detector operable. be satisfied; Utilizes picture of N-32 and determines that the instrument is NOT operable. (reference SOP-39.0 SOP-39.O section 4.1)
- a. Check N-32 Instrument power on AND control a. Lights are checked power on lights illuminated. . Instrument power light is NOT illuminated.
Control power is illuminated.
- b. Check switches aligned: b. Switches are determined;
- i. Level Trip i. Normal I.
ii.Operation Selector ii. Normal iii.High Flux at shutdown iii. Normal
- c. Performs a channel check per STP-1.0 STP- 1.0 (SR c. NOT Acceptable per STP- STP 3.9.2.1). 1.0 allowances.
FNP HLT-33 ADMIN A.1.1.A Page 44 of 10 10 EVALUATION CHECKLIST CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) S. (STEP 3.2.3)
- 5. Verify N-48, Gamma-metrics 3.2.3)Verify 5) Determines step 3.2.3 has been S/U S / U Source Range NI, detector operable. satisfied. (May identify that the (reference SOP-39.0 section 4.3) Refueling Coordinator must first be consulted.)
- a. Checks N-48 in service. a. Aligned and in service as indicated by picture and bulleted items listed on picture.
- b. Performs a channel check per STP-1.0 (SR b. Acceptable per STP-l.0 STP-1.0 3.9.2.1). Table 11 allowances.
- 6. (STEP 3.3) Reactor Coolant system 2000 ppm. 6) Determines step 3.3 has been S / U S/U satisfied; Utilizes initial conditions to verify boron concentration.
NOTE: R-S being in service OR required action being taken. The Element 7 would require either R-5 candidate might question whether or not surveys are being performed. Additionally, due to rules of usage may stop the task and attempt to notify the SS. IF required CUE: "The The SS acknowledges the issue you have identified and directs you to continue. No completed. compensatory actions have yet been completed."
- 7. (STEP 3.4.1) Verifies R-SR-5 operable/operating. R-5 is NOT
- 7) Identifies R-S S / U operable/operating; Determines step 3.4.1 has NOT been satisfied. (May annotate failure
(
Reference:
SOP-4S.0 4.1.3 TRM (
Reference:
SOP-45 .0 section 4.1.3; TRIVI 13.3.4) or need to initiate survey).
- a. Verify Operation Selector switch position. a. Level Cal.
- b. Verify Range Selector switch position. b. WIDE
- c. Verify Drawer indication lights: c. Lights are:
- i. Power i.ON
- 1. ON ii. Channel Test light
- 11. ii. ON iii. High Alarm 111. iii. OFF 111.
iv. Low Alarm IV. iv. OFF IV.
FNP HLT-33 ADMIN FNPHLT-33ADMIN A.1.1.A Page5oflO Page 5 of 10 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: STANDARDS: (CIRCLE)
- 8. (STEP 3.4.2 through 3.4.4) Verifies R-24AorB, 8) Identifies radiation monitors are SS / U R-25AorB, and R-35AorB operable using SOP- operable; Initials step 3.4.2 45.0 section 4.1.5. through 3.4.4.
(uses pictures of LOCAL radiation monitor The following indications are for indications to determine the following conditions) all steps 3.4.2 through 3.4.4:
- a. Verify local switch for vacuum pump. a. AUTO
- b. Verify LOCAL switch position. b. ON (and Fans are running)
(uses pictures of radiation monitor drawers to determine the following conditions)
- c. Verify MCR switch: c. MCR switches are:
- i. Operation selector i. Oper 1.
ii. Pump Power
- 11. ii. ON 11.
iii. Pump Start Ill. Start/Neutral iii. StartlNeutral Verify MCR lights:
- d. Verity d. MCR lights are:
- i. Power light i. ON 1.
ii. Pump ON light
- 11. ii. ON 11.
iii. Flow fault light Ill. iii. OFF Ill. iv. Alert light IV. iv. OFF IV.
- v. High light v. OFF vi. Fail/Reset light vi. ON vii. Power VII. Poweronon light vii. ON VII.
- 9. (STEP 3.5 through 3.6) Evaluates Refueling 9) Utilizes initial conditions and S / U S/U integrity has been verified within 100 hrs, and that evaluates that step 3.5 is applicable, step 3.6 is not applicable. satisfied and 3.6 in N/A.
NOTE: REVIEW of completed Appendix 6 to evaluate the above elements. CUE: UOP-4.1, Appendix 6 which are not satisfied. Identify all, if any, initial conditions listed in UOP-4.l,
- 10.Reports/annotates
- 10. Reports/annotates that step 3.2.2 and 3.4.1 are not 10) Identifies N32 inoperable, R- S / U S/U completed or satisfied and that core Alts initial 5 inoperable and that Core conditions are not satisfied. alterations should not be permitted since the initial conditions have not been satisfied.
FNPHLT-33ADMIN FNP HLT-33 ADMIN A.1.1.A Page6oflo Page 6 of 10 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) RO ONLY: Terminate when elements 1-10 of the task have been completed. SRO ONLY Cue: PROVIDE Handout #2, read and escort back to classroom to allow TS review. Based on the conditions you identified perform the following:
- 1) List all TS CONDITIONS, REQUIRED ACTIONS and COMPLETION TIMES for LCOs not met, if any.
- 11. Evaluates TS 3.9.2 Condition C: Inoperable 11) Identifies the need to S / U S
Audio Counts. IMMEDIATELY verify un un-borated water sources are isolated.
** 12. Evaluates TRM 13.3.4 condition B. 12) Identifies the need to S / U S
IMMEDIATELY notify HP to perform a survey of the SFP area within 24 hours.
- 13. Evaluates TS 3.9.2 Condition A: One source 13) Identifies an ADMIN LCO for S / U S
range neutron flux monitor inoperable. Condition A for N32 inoperable I SRO ONLY: Terminate when elements 1-13 of the task are complete. STOP TIME CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) (*) before the element number. GENERAL
REFERENCES:
- 1. UOP-4.1, VER 52
- 2. KA: # G2.1.40 2.8 3.9 G2.1.36 3.0 4.1 G2.1.32 3.8 4.0
FNP HLT-33 FNP HLT-33 ADMIN A.1.1.A A.1.1.A Page of 10 Page 77 of 10 GENERAL TOOLS TOOLS AND AND EQUIPMENT: EQUIPMENT: 1.1. References References to to be computer (using classroom computer via classroom be accessed via (using exam exam IDID logon) logon) and Exam Reference and Exam Reference disk/files only. only.
- 2. Provide UOP-4.
- 2. UOP-4.I, 1, Appendix Appendix 66
- 3. Pen/pencil
- 3. Pen/pencil Pictures of the following components: (11 pages total)
- 4. Pictures
- a. R-24A Local indications g. R24A & R25A MCR indications
- b. R-24B Local indications h. R-24B & R25B MCR indications
- c. R-25A Local indications i. R-35A & R35B MCR indications
- d. R-25B Local indications j.J. N3 N3I1 drawer indications
- e. R-35A Local indications k. N32 drawer indications
- f. R-35B Local indications 1. N3 N3I,1, N32 & N48 Board indications
- m. Audio Count Rate Channel Drawer Critical ELEMENT justification:
STEP Evaluation NOTE: (a.b.c ... ) describe the anticipated actions taken by the candidate. Completion The listed sub-steps to each element (a.b.c...) of all sub steps is not required to make the determination of operability of the components, nor is it intended that these actions be observed. These sub-steps are provided for the examiner as an evaluation tool.
- 1. criticalthis step is for satisfying site procedural protocol and expectations.
NOT critical-this
- 2. critical this step is for satisfying site level expectations or requirements.
NOT critical-
- 3. criticalAlthough Task objective-component is operable.
NOT critical-Although
- 4. Critical Element -Task Task objective-evaluate operability of required equipment.
- 5. criticalAlthough Task objective-component is operable.
NOT critical-Although
- 6. NOT critical - this step does not require any evaluation from the candidate.
- 7. Critical Element -Task Task objective-evaluate operability of required equipment.
- 8. criticalAlthough Task objective-components are operable.
NOT critical-Although
- 9. Critical Element-FINAL ElementFINAL Task objective-identifies that initial conditions are not satisfied for Core Alts.
- 10. critical this step does not require any evaluation from the candidate.
NOT critical-SRO ElementIDENTIFIES and IMPLEMENTS the Actions for License requirement. Critical Element-IDENTIFIES 11. SRO ElementIDENTIFIES and IMPLEMENTS the Actions for License requirement. Critical Element-IDENTIFIES 12. SRO criticalAdministrative LCO is for tracking purposes only. NOT critical-Administrative 13.
FNP HLT-33 FNP HL T-33 ADMIN ADMIN .1 .A A.1.1.A A.1 Page 88 of Page of 10 10 COMMENTS: COMMENTS: References expected References expected to be utilized: to be utilized: STP-1.0, section STP-1.0, section 5.22, Table 11 of 5.22, Table and Appendix Appendix 11 and of Appendix Appendix 3, Ver. 98.0; 3, Ver. check information channel check 98.0; channel information M-50 Master list of Surveillance Tests, Ver. 25.0; M-50 Master list of Surveillance Tests, Ver. 25.0; determine determine channel channel check check procedure procedure SOP-39.0, SOP-3 Nuclear Instrumentation System, 9.0, Nuclear switch al 9.0; evaluate switch System, Ver. 9.0; ignrnent/operabi lity alignment/operability SOP-45.0, Radiation Monitoring System, SOP-45.O, System, Ver. 36.0; switch alignment/operability 36.0; evaluate switch TRM 13.3.4 TRM 13.3.4 Ver 8.0, 8.0, and Basis Basis Ver 3.0. 3.0. Amendment 146 TS 3.9.2 and Basis, Amendment (U-I), Amendment 137 146 (U-i), 137 (U-2) UOP-4.I, CONTROLLING PROCEDURE UOP-4.1, PROCEDURE FOR FOR REFUELING, Ver. 52.0
'1'0 DISC;USS
[C) DISCUSS with the examiner: Due to to procedure rules of usage, a candidate may stop performing the steps upon encountering the first malfunction; therefore the candidate may not have evaluated all components/steps expected. Possible options: Brief all students verbally prior to providing the task or provide the following as part of the initial conditions: For the purposes of this task, complete the Appendix in its entirety. Any actions, permissions or notifications required by any identified discrepancies, or procedure step, will be conducted upon completion of all other steps of the Appendix. Annotate any condition identified or the action, the permission, or the notification required for discussion upon completion of the appendix for any, if any, step that can not be completed.
- Facilitate with Cues at the evaluation phase to resolve the, the expected actions while monitoring the completion of the remaining elements.
- Facilitate with Cues at the evaluation phase then return the candidate to complete the remaining elements.
Consider element #13 relative to the criteria of NON-applicable LCO application resulting in Critical Element Failure. This element is listed based on the probability that this LCO would be entered if immediate evaluation of Gamma-Metrics capability to adequately monitor the core (possible that the fuel movement that existed prior to current condition uncoupled the core with the instruments); A Mandatory application of TS 3.9.2 Condition A may be implemented, due to decision to conservatively declare inoperable until the Refueling Coordinator is consulted.
- Gamma Gamma metrics must be evaluated as coupled by Refueling Coordinator.
FNP HLT-33 ADMIN HANDOUT #2 Page 11 of I1 CONDITIONS Based on the conditions you identified evaluate TS and TRM requirements and perform the following:
- a. List all TS and TRM CONDITIONS, REQUIRED ACTIONS and COMPLETION TIMES for LCOs not met, if any.
FNP HL T-33 ADMIN FNPHLT-33ADMIN A.1.1.A A.1.1.A HANDOUT Page 11 of Page of 11 CONDITIONS CONDITIONS When II tell tell you you to begin, you you are are to perform or evaluate all perform or all steps FNP-I-DOP-4.1, Appendix 6, steps FNP-1-UOP-4.1, Verification of Initial Conditions Verification of Initial Conditions Prior Prior to to Core Core Alterations. Alterations. The The conditions under which task isis to which this task to be performed be performed are:
- a. Core Offload Core Offload waswas suspended suspended 1818 hours hours ago.
- b. 100°F.
RCS temp is 100°F.
- c. Time to boil is >2 hours.
- d. shuffle in the Spent Fuel Pool is ongoing.
A Fuel shuffle ongoing.
- e. between the MCR and Communications between and a System Operator acting as the Cavity Watch have 10 minutes ago.
verified available 10 been verified
- f. RCS boron concentration is 2450 ppm following an over boration performed last shift.
- g. Rx Makeup water is being used to dilute the Reactor Cavity by chemistrys chemistry's request.
- h. FNP-I-STP-18.4, Containment Midloop and/or Refueling Integrity Verification and FNP-1-STP-18.4, Containment Closure, was completed yesterday at 1400.
i.1. CTMT Main Purge system is in operation.
- j. The equipment hatch and all containment air locks are currently closed.
- k. The Ctmt Evacuation alarm is sounding inside Containment.
- 1. The Audio Count Rate Channel is NOT producing any audible noises.
- m. Applicable equipment will be assessed using the provided photographs.
- n. You have been directed to perform or evaluate all steps of FNP-1-UOP-4.1, Appendix 6.
ofFNP-I-DOP-4.1,
- o. UOP-4. 1, Appendix 6, which are not Identify all initial conditions for core alterations listed in DOP-4.1, satisfied, if any.
12/09/09 14:42:20 12/09/09 14:42:20 FNP1-UOP-4.1 FNP-I-UOP-4.1 APPENDIX 66 VERIFICATION OF INITIAL CONDITIONS PRIOR TO CORE AL ALTERATIONS TERATIONS Performed by: Date Reviewed by: by: Date This This appendix appendix consists of 22 pages consists of pages Version 52.0 Version 52.0
12/09/09 14:42:20 FNP-1-UOP-4.1 APPENDIX 6 APPENDIX 6 VERIFICATION OF INITIAL CONDITIONS PRIOR TO CORE AL ALTERATIONS TERA TIONS
1.0 Purpose
Provide separate guidance for specific initial conditions which will be needed to be verified more than once due to core alterations occurring at various time during an outage period. 2.0 Initial Conditions: 2.1 The version of this appendix is the current version. (OR 1-98-498) 2.2 This appendix is correct for the unit for which the task applies. (OR 1-98-498)
3.0 Instructions
NOTE: This appendix should be completed each time core alterations are commenced, including suspensions of core alterations exceeding 12 hours. 3.1 The direct communications system between the control room and the reactor _1-/ cavity is verified available for use within one hour prior to core alterations. CAUTION: The Gamma-Metrics source range channel may only be used as a back-up to N-31 or N-32 during certain core configurations. The Refueling Coordinator should be consulted ifN-31if N-31 or N-32 becomes inoperable when the core is not fully loaded. 3.2 Verify at least two of the required source range neutron flux monitors are operable with continuous visual indication in the Control Room and a channel check performed within 12 hours prior to any core alterations. Trip functions and associated TSLBs are not required for Mode 6 or core alterations. 3.2.1 Source Range Nuclear Instrument, Channel N-3 N-311 3.2.2 Source Range Nuclear Instrument, Channel N-32 3.2.3 Gamma-Metrics Neutron Flux Monitor, Channel N-48 of 2 Page 11 of2 Version 52.0
12/09/09 14:42:20 12/09/09 14:42:20 FNP-1-UOP-4.1 FNP-1-UOP-4.1 APPENDIX APPENDIX 66 3.3 3.3 The reactor The reactor coolant system boron coolant system concentration is> boron concentration is:::: 2000 2000 ppm. ppm. 3.4 3.4 operation per FNP-1-SOP-45.0, The following radiation monitors are in operation FNP-1-S0P-45 .0, RADIA TION MONITORING SYSTEM, RADIATION SYSTEM, or required action is being taken per Tech. Specs Specs 3.3.6, 3.3.6, 3.3.7, 3.3.8, and TR 13.3.4. 3.3.7, and 3.3.8, 13.3.4. 3.4.1 3.4.1 R-5 Spent fuel storage or portable instrumentation used to portable monitoring instrumentation monitor SFP area at least once per 24 hours (for fuel movement in SFP). 3.4.2. R-25A or B B Spent fuel storage - Gaseous (for fuel movement in SFP). 3.4.3 R-24A or B - Containment purge system with main or mini purge in operation. 3.4.4 R-35A or B - Control Room HVAC
- HVAC 3.5 Refueling integrity has been verified per FNP-1-STP-18.4, CONTAINMENT
_/- / MID LOOP AND/OR REFUELING INTEGRITY VERIFICATION AND MIDLOOP CONTAINMENT CLOSURE within 100 hours prior to the start of core alterations. alterati ons. 3.6 IF the containment equipment hatch, personnel air lock, or auxiliary air lock is jf open during core alterations and/or during movement of irradiated fuel assemblies within containment, THEN ensure the following items are complete (TS 3.9.3): _/- / 3.6.1 A designated, trained Maintenance Closure Response Team (MCRT) Ivuvl MM is available to shut the containment equipment hatch, a door in the personnel air lock, and a door in the auxiliary air lock within two hours after notification and direction from the control room. _/- / 3.6.2 For the equipment hatch, the surveillance is current for SR 3.9.3.3, i.e., FNP-0-STP-6 10.0 FNP-O-STP-61 0.0 has been completed by Maintenance within the last seven days Page 2 of2 Page of 2 52.0 Version 52.0
NUCLEAR INSTRUMENTATION PROTECTION CHANNEll. CHANNEL I SOURCE RANGE xoo
/
N1C55N10031 WSTRENT PQd!RON IISV, 5A, AC IIBV,5A,AC 118V.5A,AC IHSW COf4TROl. CONTROL POWER POWER
C) C) -I .: 1) 118V.5A,AC CONTROL POWER
) 0>
-rn o oP z j L_J
MCB instrumentation instrumentation Gamma Metrics Local indications: I 48A 486 0o HSDP Excore EQ EQ 10 I
- 100 Neutron Monitor 10 N-48 breaker, 10 01 R21 L005A QIR2ILOO5 A is 10 10 closed.
10 0o The nonoperate
.10 LED is not 10 illuminated.
4 10
- 10 10
r power pump on Putnp Functø 4d fauft E top
*IJT1IE.
pa er purge off off on norrn prog. I V*CTc7cIEEN] L. Pump Function
of t R2E3 CTMT PURGE oprri
, t
aternaier Function Switch caI hv. power pump off I oper cpm fli vQIC do rOWNY OtVOON alert 4? \ c. e pfl R-358 CONT RM PiILET AIR
CONT PURGE R-24B INDICATIONS LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running. Pump Function Switch
CONT PURGE R-24A INDICATIONS LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running. Pump Function Switch
CONT RM AIR SUPPLY R-35A INDICATIONS LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running. Pump Function Switch
CONT RM AIR SUPPLY R-358 R-35B INDICATIONS LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running. CONT RM AIR SUPPLY RC R-35B Pump Function Switch
FUEL BLDG R-25B cp m flOIt5 dc INDICATIONS LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running. Pump Function Switch
FUEL BLDG R-25A INDICATIONS LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running. TDREN Pump Function Switch
HLT-33 ADMIN FNP HLT-33 Page 11 of 55 Conduct of Operations ADMIN G2.1.25 - SRO A.1.2.S Conduct A1.2.S TITLE: Conduct A Shutdown Safety Assessment and Determine Time to Saturation. PROGRAM APPLICABLE: SOT SOCT____ SOCT OL T ---.2L OLT LOCT_ _ X LOCT____ ACCEPTABLE EVALUATION METHOD: ---.2L.. X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM XX CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: SIMULATORICNUMBER: NIA N/A ALTERNATE PATH TIME CRITICAL PRA_ _ PRA_____ JPM DIRECTIONS:
- 1. Initiation of task may be in group setting; evaluation performed individually upon completion of the task by reviewing the completed form.
- 2. Provide the examinee with the required materials to perform this JPM.
- 3. The actions of step 4.2 of the Appendix have been completed and information may be provided to examinee, if requested.
TASK STANDARD: Required for successful completion of this JPM:
- of UOP-4.0.
Correctly Assess Time to Saturation using TABLE A ofUOP-4.0.
- of UOP-4.0.
Complete the Core Cooling section of a Shutdown Safety Assessment using Fig 1A ofUOP-4.0. Examinee: Overall JPM Performance: Satisfactory 0 Unsatisfactory 0D Evaluator Comments (attach additional sheets if necessary) EXAMINER: EXAMINER: _________________ Developer H. Fitzwater 10/26/09 10/26109 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLT-33 FNP HL T-33 ADMIN ADMIN A.1.2.S A.1 .2.S Page 22 of Page of 55 CONDITIONS CONDITIONS When I tell you to begin, you are to determine When I tell you to begin, you are to determine the the time time to to saturation saturation andand prepare the CORE prepare the CORE COOLING SECTION COOLING SECTION ONLY ONLY of of aa shutdown safety assessment on shutdown safety Unit 11 per on Unit per FNP-0-UOP-4.O, FNP-0-UOP-4.0, Appendix 1, 1, step 4.3 and step 4.4. The conditions under which this task is to be performed step 4.4. performed are: are:
- a. Unit 1I is in a Refueling Outage, and has been been shutdown for 120 120 hours.
- b. IA IA SG SG wide range range level level is is 74%; IB lB SG SG wide range level level is 75%; I C SG wide range level is 1C 10%.
10%.
- c. RCS temperature is 117°F.1 17°F.
- d. The SS has not permitted interpolation between data points.
- e. The RCS is at mid-loop with a FULL core.
- f. Both trains of RHR are in operation in the cooldown mode.
- g. STP-18.4 has been verified current.
Mid-loop integrity per STP-18.4
- h. The IPC is not available.
i.1. Another operator is evaluating the other SHUTDOWN SAFETY FUNCTION/CRITERIAS. j.J. You are directed to determine the time to saturation and prepare the CORE COOLING SECTION ONLY of a shutdown safety assessment on Unit II per FNP-0-UOP-4.0, Appendix 1, step 4.3 and step 4.4. INITIATING CUE: "You You may begin." begin. EVALUATION CHECKLIST EVALUATION RESULTS: ELEMENTS: STANDARDS: (CIRCLE) (CIRCLE) START TIME NOTE: Since task may be performed as a group classroom task, elements 11 through 8 may be evaluated by reviewin reviewing the com leted paperwork. completed a erwork.
- I.
- 1. PER STEP 4.3, determine and document at 1) Written in bottom line of SS/U I U bottom of Figure lA: 1A: Figure IA:1A:
Time to saturation IF core cooling were lost: (a). 0.0 hours.
-.lliL J hours JQL JL minutes (b). 9.2 minutes.
- Select Table using given data °° Table A (Full Core)
- Select applicable page of table.
Select °° Select page Select page 2 of 3 (120°F)
- Select Select column for given RCS level °° Select column Select (MIDLOOP) column 2: (MIDLOOP)
- Select row for time after after Shutdown Shutdown °° Select row 66 (120 hours)
- Identify time °° Identify 9.2
- Identify units for time °° Identify "min" mm from column header header NOTE:
NOTE: For For Element Element numbers numbers 22 through through 7, 7, the the "LINE" LINE number to the correlates to number correlates Core Cooling the Core Shutdown Cooling Shutdown Safety Safety Function Function Evaluation, Evaluation, Figure Figure IA1A of Appendix II ofFNP-0-UOP-4.0. of Appendix Elements 22 through of FNP-0-UOP-4.0. Elements through 88 are per step 4.4 of the appendix. are per step 4.4 of the appendix.
FNPHLT-33ADMIN FNP HL T-33 ADMIN A.1.2.S Page3of5 Page 3 of 5 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE)
** 1:> 2 SGs Avail with loops filled (Ref.
- 2. LINE 1:22 2) Zero (0) written on the line for S / U S
step 2.7).- evaluate SG availability: item 1. SG tubes filled and vented; considered filled o Midloop f. filled and vented
>100 psig if RCS has remained ::::.100 and vented ifRCS < 100 psig and <
since last fill and vent.
** level 152'
- 3. LINE 2:Cavity level::::. 152 9" 9 3) Zero (0) written on the line for S / U S
item 2.
** 4. LINE 3:RHR subsystems Available (0,1, or 2) 4) Two (2) written on the line for S / U S
item 3.
** level> 126'
- 5. LINE 4:RCS level::::, 126 6" 6 5) Zero (0) written on the line for S S / U item 4.
** 6. LINE 5:Time to saturation >30 minutes OR RCS 6) Zero (0) written on the line for S / U press >325 psig with at least one RCP available item 5.
for operation and at least one SG available
- 7. Core Cooling Subtotal 7) Two (2) written on line for Core S / U Cooling Subtotal.
NOTE: Since determination of the Core Cooling function is the critical element, and depending on the format of administering this JPM, the examinee may stop performing the Appendix upon discoverin discovering the ORANGE condition and may not complete element 8. IF no condition circled for element 8 THEN provide the following CUE: What condition is Core Coolin "What Cooling in?"in?
** 8. Evaluates Core Cooling condition 8) Circle around ORANGE SS / U condition for the Core Cooling Function OR., if cued per NOTE State the condition is ORANGE I Terminate when all elements of the task have been completed.
STOP TIME CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) (*) before the element number.
FNP HLT-33 HL T-33 ADMIN A.1.2.S A.1 .2.S Page 4 of 55 GENERAL
REFERENCES:
- l. FNP-0-UOP-4.0, VER
- 1. VER 36.0 36.0
- 2. KA: G2.1.25 RO 3.9 3.9 SRO 4.2 GENERAL TOOLS AND EQUIPMENT:
- l. References to be accessed via classroom computer (using exam ID logon) and Exam Reference 1.
disk/files only. disklfiles
- 2. Provide copy of FNP-0-UOP-4.0 Table A, Table B, Appendix 11 ofFNP-0-UOP-4.0
- 3. Pen/Pencil
- 4. Calculator (optional-not required to complete this task)
Critical ELEMENT justification: STEP Evaluation l.
- 1. Critical this is first of the two major objectives of the task. Utilization of the plant parameters and selection of the appropriate table are required to properly assess Shutdown Core Cooling function.
2. Critical Each line item is critical to evaluate proper assessment of each parameter. 3. The aggregate effect of errors made within each line could result in obtaining the 4. correct end point; therefore each sub-step must be evaluated to ensure examinee is 5. correctly assessing the parameters. 6.
- 7. This is NOT a critical element since documentation of this summation is not procedurally driven nor will failure to complete this element necessarily impact the outcome.
- 8. Critical This is the final objective of the task; proper assessment of this function is required to identify the need of mitigating actions necessary to ensure the health and safety of the public is not jeopardized.
COMMENTS: References expected to be utilized:
- 1. FNP-0-UOP-4.0, ver 36.0
1 Header information is not required for this Task; but if requested use current date and time. Name Prepared By: Prepared By:-,:I=N=am=e===-_ _ App-i, App-!, Fig Fig 22 Evaluated Evaluated LI 0 SHUTDOWN SAFETY SHUTDOWN FUNCTIONI CRITERIA SAFETY FUNCTION! CRITERIA CONDITION (No/False=O, Yes/Truel, (No/FaIseO, Yes/True=l, Use number within Use number within range range when when required) required) (Circle Condition) (Circle Condition) REACTIVITY Subtotal Subtotal Condition Condition AOP AOP l.
- 1. No Core No Core Alterations Alterations in in Progress Progress a-I 0-1 RED RED 41 41 2.
- 2. Number of Number of Boration Boration Flow Flow Paths (0, 1,1,2)
Paths (0, (Ref step
- 2) (Ref 2.13) step 2.13) 22 ORANGE ORANGE 41 41
- 3. RCS Boron:
Boron: CSD/Refueling CSD/Refueling Concentration Concentration 34 3-4 YELLOW 41 41
- 3. RCS 55 GREEN GREEN 4.
- 4. Source Range Instrumentation Source Instrumentation Available Available (GREEN (GREEN if Defueled) ifDefueled)
Subtotal Reactivity Subtotal Reactivity CORE COOLING Subtotal Subtotal Condition Condition AOP AOP l.
- 1. :2: 22 SOs SGs Avail with loops filled (Ref step 2.7) 0 0-I 0-1 1t'~1III! .Jl~ !til!!
RED
!A1I'f *Y"'!! !1ft" ~EII!! !!Alii!
42
~., -{IIII!! !!.&"'!! !!1,
- 2. 152'9" level:2: 1529 Cavity level
_2 0 2 _ ~{~'i"J-i*'~I~~,;;JJ,;;JJt~J_'*',",J
- 3. Subsystems Available (0, 1 RHR Subsystems 1 or 2)
_ 00 _ 5
~5 GREEN
- 4. RCS level :2: 126 126' 6 6" (GREEN if Defueled) Mm Min required is to
- 5. saturation>
Time to saturation > 30 minutes OR RCS press press> 325 psig with at least
> 325 00
----- "CIRCLE" the CIRCLE one RCP available for operation and at least one SG available 22 condition Core Cooling Subtotal ORANGE "ORANGE" POWER AVAILABILITY Subtotal Condition l.
- 1. 11 A "A" Train DG Available 0-2 RED including the
- 2. 1I B "B" Train DO DG Available 33 ORANGE subtotal or the AOP F 4160 V BUS normal (Aligned to A SUT) 4-5 YELLOW
- 3. is not required.
6 GREEN
- 4. G 4160 V BUS normal (Aligned to B SUT)
- 5. 22 Feeds available to the HV Switchyard (0, I1 or 2)
Power Availability Subtotal CONTAINMENT Subtotal Condition AOP l.
- 1. Refueling Integrity Set 0-I 0-1 RED 44
- 2. CTMT Closure Set 2-4 ORANGE 44
- 3. No Core Alterations in Progress (2 pts) 5-6 YELLOW 44
- 4. Equipment Hatch & Air Locks Closed or Capable of Being Closed on 7 GREEN Short Notice if Defueled)
(GREEN ifDefueled)
- 5. RCS level :2: 126' 6" RCSlevel126 6 (3 pts)
Containment Subtotal INVENTORY Subtotal Condition AOP l.
- 1. Cavity 23 Feet (142'1")
Refueling Cavity:2: (i42i) Above Fuel a0 RED 45
- 2. LHSI Pump/Flowpath Available 1I ORANGE 45 45 2 YELLOW 45
- 3. HHSI Pump/Flowpath Available 3-4 GREEN
- 4. RCS is Intact below the Reactor Vessel Flange (GREEN if Defueled)
Inventory Subtotal RCS INTEGRITY Subtotal Condition AOP l.
- 1. All S/G Manways or Nozzle Dams Installed 0-I 0-1 ORANGE 46
- 2. RCS is Intact below the Reactor Vessel Flange 2 YELLOW 46
- 3. Pressurizer level < < 100% 3 GREEN if Defueled)
(GREEN ifDefueled) RCS Integrity Subtotal SPENT FUEL COOLING SPENT Subtotal Condition AOP l.
- 1. SFP level :2: 23 feet (151' SFP 6") above fuel (4 pts)
(1516) 0-4 RED 47 47
- 2. A Trn Tm SFP SFP Cooling Cooling available available 5 ORANGE ORANGE 47 66 YELLOW 47 47
- 3. B Trn Tm SFP SFP Cooling available available 7 GREEN
- 4. :2: 2 SFPSFP Makeup Sources Sources (RWST, (RWST, DW, RMW to Blender, Boric Boric Acid to Blender, RHT to transfer canal with weir gate gate removed)
SFP 5FF Subtotal Subtotal r I I I 0 9.2 i Time Time to saturation saturation IF corecore cooling cooling were lost:lost:
° hours minutes minutes Current Version Current Version Page 6 of 18 18
FNP HLT-33ADMIN HLT-33 ADMIN A.1.2S HANDOUT Pg 11 of I1 CONDITIONS When II tell you to begin, you are to determine the time to saturation and prepare the CORE COOLING SECTION ONLY of a shutdown safety assessment on Unit 1 1 per FNP-O-UOP-4.O, Appendix 1, step 4.3 and step 4.4. The conditions under which this task is to be performed are:
- a. Unit 1I is in a Refueling Outage, and has been shutdown for 120 hours.
- b. lA1A SG wide range level is 74%; lB lC SG wide range level is IB SG wide range level is 75%; 1C 10%.
- c. RCS temperature is 117°F.
- d. The SS has not permitted interpolation between data points.
- e. The RCS is at mid-loop with a FULL core.
- f. Both trains of RHR are in operation in the cooldown mode.
- g. Mid-loop integrity per STP-18.4 has been verified current.
- h. The IPC is not available.
- i. Another operator is evaluating the other SHUTDOWN SAFETY FUNCTION/CRITERIAS.
1.
- j. You are directed to determine the time to saturation and prepare the CORE COOLING SECTION ONLY of a shutdown safety assessment on Unit 11 per FNP-0-UOP-4.0, Appendix 1, step 4.3 and step 4.4.
11/13/09 12:03:44 FNP-0-UOP-4 .0 FNP-0-UOP-4.0 TABLE A TABLE A Power-Uprated Power-Up rated Unit Time To Saturation: Full Core Assumed Initial Temperature = 100°FlOO°F Time Time To Time To Time To Time To After Saturation Saturation Saturation Saturation RCS Shutdown at Midloop 33 ft Below Flange Full Reactor Cavity Full (hours) (min) (mm) (min) (mm) (hours) (hours) 40 7.7 10.5 5.6 1.3 60 8.7 11.9 6.3 1.4 80 9.5 13.0 6.9 1.6 100 10.4 14.2 7.5 1.7 120 11.3 15.4 8.2 1.9 140 11.9 16.3 8.6 2.0 160 12.7 17.4 9.2 2.1 180 13.3 18.2 9.6 2.2 200 13.9 19.0 10.1 2.3 336 17.1 23.4 12.4 2.9 504 20.8 28.5 15.1 3.5 VOLUME REFERENCE TABLE Midloop Volume (ft3): 945 Volume: 3 ft Below Flange (ft3) 348 Total =
= 1293 Volume: Full Reactor Cavity (ft3) 39750 Total =
= 41043 Volume: RCS Full (including pzr)
Pzr) (ft3) 9591 of 3 Page 11 of3 Version 36.0
11/13/09 12:03:44 11113/09 FNP-0-UOP-4.0 TABLE A TABLE A Power-Up rated Unit Power-Uprated Time To Saturation: Full Core Assumed Initial Temperature = = 120°F Time Time To Time To Time To Time To After Saturation Saturation Saturation Saturation RCS Shutdown at Midloop 33 ft Below Flange Full Reactor Cavity Full (hours) (mm) (min) (mm) (min) (hours) (hours) 40 6.3 8.6 4.5 1.1 60 7.1 9.8 5.2 1.2 80 7.8 10.6 5.6 1.3 100 8.5 11.7 6.2 1.4 120 9.2 12.6 6.7 1.6 140 9.8 13.4 7.1 1.7 160 10.4 14.2 7.5 1.8 180 10.9 14.9 7.9 1.8 200 11.4 15.6 8.2 1.9 336 14.0 19.1 10.1 2.4 504 17.0 23.3 12.3 2.9 VOLUME REFERENCE TABLE Midloop Volume (ft3): 945 Volume: 33 ft Below Flange (ft3) 348 Total =
= 1293 Volume: Full Reactor Cavity (ft3) 39750 Total =
= 41043 Pzr) (ft3)
Volume: Full RCS (including pzr) 9591 of 3 Page 2 of3 Version 36.0
11/13/09 12:03:44 FNP-0-UOP-4.0 TABLE A TABLE A Power-Uprated Unit Time To Saturation: Full Core Assumed Initial Temperature == 140°F Time Time To Time To Time To After Saturation Saturation Saturation Time To Saturation Shutdown at Midloop 33 ft Below Flange Full Reactor RCS Full (hours) (mm) (min) (mm) (min) Cavity (hours) (hours) 0.8 40 4.9 6.7 3.5 0.9 60 5.6 7.6 4.0 4.4 1.0 80 6.1 8.3 1.1 100 6.6 9.1 4.8 1.2 120 7.2 9.8 5.2 140 1.3 7.6 10.4 5.5 1.4 160 8.1 11.1 5.9 1.4 180 8.5 11.6 6.1 1.5 200 8.9 12.1 6.4 10.9 14.9 1.8 336 7.9 504 13.3 18.2 2.2 9.6 VOLUME REFERENCE TABLE Midloop Volume (ft3): 945 Volume: 33 ft Below Flange (ft3) 348 Total =
= 1293 Volume: Full Reactor Cavity (ft3) 39750 Total =
= 41043 (including Pzr) (ft3)
Volume: Full RCS (includingpzr) 9591 Page 33 of3 of 3 Version 36.0
11113/09 11/13/09 12:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4 .0 TABLEB TABLE B TABLE B TABLEB Power-Up rated Unit Power-Uprated Time To Saturation: One-Third New Fuel 100°F Assumed Initial Temperature == lOO°F Time Time To Time To Time To Time To After Saturation Saturation Saturation Saturation RCS Shutdown at Midloop 3 ft Below Flange Full Reactor Full (hours) (mm) (min) (min) (mm) Cavity (hours) (hours) 100 15.6 21.4 11.3 2.6 200 20.9 28.5 15.1 3.5 300 24.7 33.7 17.8 4.2 400 27.5 37.6 19.9 4.7 500 31.1 42.5 22.5 5.3 600 34.5 47.3 25.0 5.8 700 37.2 51.0 27.0 6.3 800 40.4 55.3 29.2 6.8 VOLUME REFERENCE TABLE Midloop Volume (ft3): (ft3): 945 Volume: 3 ft Below Flange (ft3) 348 Total =
= 1293 Volume: Full Reactor Cavity (ft3) 39750 Total =
= 41043 Volume: Full RCS (including pzr)Pzr) (ft3) 9591 Page 11 of3 Version 36.0
11113/09 11/13/09 12:03:44 FNP-0-UOP-4.0 TABLE TABLEBB TABLE TABLEB B Power-Uprated Power-Up rated Unit Time To Saturation: One-Third New Fuel Assumed Initial Temperature = 120°F Time Time To . Time To Time To Time To After Saturation Saturation Saturation Saturation RCS Shutdown at Midloop 33 ft Below Flange Full Reactor Full (hours) (mm) (min) (mm) (min) Cavity (hours) (hours) 100 12.8 17.5 9.2 2.2 200 17.1 23.4 12.4 2.9 300 20.2 27.6 14.6 3.4 400 22.5 30.8 16.3 3.8 500 25.4 34.8 18.4 4.3 600 28.3 38.7 20.5 4.8 700 30.5 41.7 22.1 5.2 800 33.0 45.2 23.9 5.6 VOLUME REFERENCE TABLE Midloop Volume (ft3): 945 Volume: 33 ft Below Flange (ft3) 348 Total == 1293 Volume: Full Reactor Cavity (ft3) 39750 Total =
= 41043 Pzr) (ft3)
Volume: Full RCS (including pzr) 9591 of 3 Page 2 of3 Version 36.0
11/13/09 12:03:44 FNP-0-UOP-4.0 TABLE TABLEB B TABLE TABLEB B Power-Uprated Unit Time To Saturation: One-Third New Fuel Assumed Initial Temperature = 140°F Time Time To Time To Time To Time To After Saturation Saturation Saturation Saturation RCS Shutdown at Midloop 33 ft Below Flange Full Reactor Full (hours) (mm) (min) (mm) (min) Cavity (hours) (hours) 100 10.0 13.6 7.2 1.7 200 13.3 18.2 9.6 2.2 300 15.7 21.5 11.4 2.7 400 17.5 24.0 12.7 3.0 500 19.8 27.1 14.3 3.3 600 22.0 30.1 15.9 3.7 700 23.7 32.5 17.2 4.0 800 25.7 35.2 18.6 4.3 VOLUME REFERENCE TABLE Midloop Volume (ft3): 945 Volume: 33 ft Below Flange (ft3) 348 Total =
= 1293 Volume: Full Reactor Cavity (ft3) 39750 Total =
= 41043 Pzr) (ft3)
Volume: Full RCS (including pzr) 9591 of 3 Page 3 of3 Version 36.0
11/13/09 12:03:44 11113/09 FNP-0-UOP-4.0 APPENDIX 11 FARLEY F ARLEY NUCLEAR PLANT SHARED UISTIT UNIT OPERATING PROCEDURE UOP-4.0 APPENDIX 11 1.0 Purpose of the Shutdown Safety Assessment is to provide a means for evaluating the The purpose ofthe safety condition of the plant when in Modes 4,5,6 4, 5, 6 or de-fueled and to provide appropriate contingency actions. (CR 2004102447) 2.0 Definitions 2.1 Green Condition - The plant is fully capable of performing the associated safety function. 2.2 - plant's ability to perform the associated safety function is Yellow Condition - The plants reduced but is at an acceptable level. 2.3 Orange Condition - The plants
- plant's ability to perform the associated safety function has been severely reduced and steps should be taken to minimize the amount of time in this condition.
2.4 Red Condition - The plants
- plant's ability to perform the associated safety function is in jeopardy and steps must be taken immediately to correct the cause of the condition.
2.5 Source Range Instrumentation Available - The audible count rate and at least one indication of source range counts (preferably NR-45) are available to indicate a dilution of the RCS. 2.6 RCS Intact Below the Vessel Flange - No opening exist which would result in spillage if the RCS level was raised to the vessel flange. 2.7 One or More SGs Available - A S/G is available to remove heat if the tubes are filled and vented, the wide range level is:::: is> 75%, a steam flow path to the atmosphere can be made available with minor valve manipulations and a means of adding water to the S/G via the auxiliary feed water system exists. The S/G tubes are considered filled and vented if the RCS has been maintained greater than or equal to 100 psig since the last RCS fill and vent. 2.8 RHR Subsystems Available - The RHR system is capable of removing heat from the RCS. Page 11 of 18 Version 36.0
11113/09 12:03:44 11/13/09 12:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 11 2.9 2.9 One Available - The DIG Available One DIG - The selected selected DIG capable of is capable DIG is of being started (either being started (either manually manually or or automatically) automatically) and and supplying supplying 4160 4160 V V power power to to its its respective respective bus. bus. 2.10 Equipment Hatch & Airlocks Capable of Being Closed on Short Notice - The equipment hatch meets this definition when the MCRT is established. The personnel and aux airlocks meet this definition when a routine check of the hoses and cables going through the airlocks reveals that at least one door in each airlock can be closed in less than the current time to boil. (Al(AI 2008207932) 2008207932) 2.11 HHSI Pump I Flow Path Available - A charging pump is capable of injecting water into the RCS from the RWST which contains> 50,000 gallons of water. Only minor valve manipulations are required. 2.12 LHSI Pump /FlowI Flow Path Available - A RHR pump is capable of injecting water into the RCS from the RWST R WST which contains> 50,000 gallons of water. Only minor valve manipulations are required. 2.13 Based on the unit outage, boration flow paths via charging pumps and ECCS injection lines are determined using the guidance of Table 4 of FNP-1-STP-2.1 FNP-I-STP-2.1 OR FNP-2-STP-2.1 ,BORON , BORON INJECTION FLOW PATH VERIFICATION VERlFICA nON BORIC ACID TRANSFER PUMP OPERABILITY TEST, MODES 55 & AND BORlC &6 AND by a current FNP-1-STP-3.2 OR FNP-2-STP-3.2, BORA BORATED TED WATER SOURCE OPERABILITY TEST MODE 5, 5,6. 6. Additionally, Normal charging can be considered an available boration flow path under the following conditions: 2.13.1 QIE21MOV8107 Q1E21MOV81O8 are open, OR Q1E21MOV81O7 and Q1E21MOV8108 Q2E21M0V8108 are open. Q2E21MOV81O7 and Q2E21MOV8108 Q2E21MOV8107 2.13.2 With one of the following charging pump requirements met.
- 1A or 2A Charging Pump available lA
- lB Charging Pump Available with Q1E21MOV8132A and B open, OR 1B Q2E21M0V8132A and B open 2B Charging Pump Available with Q2E21MOV8132A
- lC Q1E21MOV8132A and B open, OR 1C Charging pump available with QIE21MOV8132A 2C Charging pump available with Q2E21MOV8132A and B open 18 Page 2 of 18 Version 36.0
11/13/09 12:03:44 11113/09 FNP-0-UOP-4.0 APPENDIX 11 3.0 Precautions and Limitations 3.1 The Shift Supervisor will evaluate the affect of removing shutdown safety equipment from service. If proposed changes to the schedule appear to reflect a reduction in the key safety functions, refer the proposed changes to the Outage Manager for assessment per FNP-0-AP-94, OUTAGE NUCLEAR SAFETY, prior to implementing the changes. 3.2 The appropriate AOP-40 series procedure will be implemented upon unexpected entry into or discovery of the existence of a Red, Orange or Yellow condition. 3.3 Intentional entry into a red condition must be approved by the Plant Manager and documented per FNP-0-AP-94, OUTAGE NUCLEAR SAFETY. FNPs FNP's current position is that the plant will not be intentionally placed in this condition. FNP's commitment to NUMARC 91-06. Review FNPs 9 1-06. 3.4 Intentional entry into an orange condition must be approved by the Outage Manager or his designee prior to entry into that condition and documented per FNP-0-AP-94. 3.5 Intentional entry into a yellow condition must be approved by the Shift Manager or Operations Superintendent prior to entry into that condition. 3.6 Notify the Outage Manager immediately if a red condition or an unexpected orange condition exists. 4.0 Instructions NOTE: ** The Shutdown Safety Assessment form may be a two-side copy copy..
- The Shift Supervisor will ensure that the appropriate Shutdown Safety Assessment Form is completed at about 0200 and 1400 when in Mode 4, Mode 5, Mode 6 or defueled. (CR 2004102447) 4.1 Obtain a copy of the appropriate Shutdown Safety Assessment form. For modes 5, 6, and defueled use Figure 1A and for mode 4 use Figure lB.
4.2 Fill in the header information on the form.
- Unit
- Prepared By
- Date
- Time Page 3 of 18 Version 36.0
11113/09 12:03:44 11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 11 APPENDIX 4.3 4.3 IF in IF mode 55 or in mode 6, THEN or 6, THEN determine the time determine the time to saturation for existing to saturation existing plant plant conditions using the conditions IPC (preferred) the IPC (preferred) or or FNP-0-UOP-4.0 Table or B. Enter Table A or B. Enter time time on Figure lA of Appendix 1. Figure 1A 1. 4.4 Evaluate the criteria listed below each Shutdown Safety Function as follows. Shutdown Safety NOTE: Refer to Definitions to assist in the evaluation as appropriate. 4.4.1 IF the reactor is defueled, THEN N/A N/A the blanks for all Safety Functions except power availability and spent fuel cooling. 4.4.2 IF the criteria is met, THEN place a 11 in its blank or use the number/range of numbers listed in (). ( ). 4.4.3 IF the criteria is NOT met, THEN place a 00 in its blank. 4.4.4 For each individual Safety Function add up the numbers in the blanks and circle the condition corresponding to the subtotal. 4.5 IF an unexpected Red, Orange or Yellow condition is determined to exist, THEN implement the appropriate AOP-40 series procedure referenced on the Shutdown Safety Assessment form. 4.6 IF a yellow or orange condition exists that result in a single train available, THEN place a caution sign concerning equipment required for a safe shutdown condition at the applicable locations per the following: 4.6.1 Use Figure 2 to determine posting requirements. 4.6.2 Check the box on Figure lA lB to indicate the review of the Figure 2 1A or IB {AI 2001203573). posting requirements {AI2001203573}. 4.7 If a red, orange, or yellow condition currently exists for any Safety Function due to an intentional entry, verify 4.7.1 Appropriate approval per FNP-0-AP-94 has been obtained, and 4.7.2 Contingency Actions per Table 11 have been performed for the affected Shutdown Safety Functions. Page 4 of 1818 Version 36.0
11/13/09 12:03:44 11/13/09 12:03 :44 FNP-0-UOP-4.0 APPENDIX 11 4.8 Evaluate the activities planned 12 hours to determine if the plant may planned for the next 12 potentially potentially enter a red, orange, or yellow condition. 4.8.1 IF intentional entry into a red condition is expected THEN entry must be approved by the Nuclear Plant General Manager and documented per FNP-0-AP-94, OUTAGE NUCLEAR SAFETY. FNPs FNP's current position is that the plant will not be intentionally placed in this condition. Review FNP's commitment to NUMARC 991-06. FNPs 1-06. 4.8.2 IF intentional entry into an orange condition is expected THEN A. Entry must be approved by the Outage Manager or his designee prior to entry into that condition and documented per FNP-0-AP-94. B. Perform the Contingency Actions in Table 2 for the affected Shutdown Safety Function(s). 4.8.3 IF intentional entry into a yellow condition is expected THEN A. Entry must be approved by the Shift Manager or Operations Superintendent prior to entry into that condition and documented per FNP-0-AP-94. B. Perform the Contingency Actions in Table 2 for the affected Shutdown Safety Function(s). 4.9 Post the Shutdown Safety Assessment at the following locations.
- Control Room
- Entrance to the PAP
- Entrance to the SAP (only required if SAP opened for protected area access)
- Outage Control Center 5.0 References 4.1 NUMARC 91-06, 9 1-06, Guidelines For Industry Actions To Assess Shutdown Management.
4.2 10CFR50.65 10CFR5O.65 (a)(4) 4.3 NUMARC 93-01,93-0 1, Section 11, Assessment of Risk Resulting from Performance of Maintenance Activities, February 2, 2000. 4.4 FNP-0-AP-94, OUTAGE NUCLEAR SAFETY. Page 5 of 18 Version 36.0
11113/09 11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 11 Figure IA SHUTDOWN SAFETY ASSESSMENT (Modes 5, 6 and Defueled) By: _ _ _ _ _ _ _ _ Date: _ _ _ _Time:______ Unit:_ Prepared By:__________________ Time:___ App-l, Fig 2 Evaluated App-i, 0 LI SHUTDOWN SAFETY FUNCTION! FUNCTION/ CRITERIA CONDITION II (Circle Condition) (NoIFalseO, Yes/True=1, 'ilUI;;' 1, Use number withinwith' range whenn required) REACTIVITY Subtotal Condition AOP I.l. No Core Alterations in Progress 0-1 RED 41
- 2. Number of Boration Flow Paths (0, 1,2) 1, 2) (Ref step 2.13) 2.l3) 22 ORANGE 41 3-4 YELLOW 41
- 3. RCS Boron: CSD/Refueling Concentration 55 GREEN
- 4. Source Range Instrumentation Available (GREEN if Defueled)
. ifDefueled)
Reactivity Subtotal CORE COOLING Subtotal Condition AOP 1.
- l. SOs Avail with loops filled (Ref step 2.7)
;;:: 2 SGs 01 0-1 RED 42 2-3 ORANGE 42
- 2. Cavity level 1529 level;;:: 152 '9" 4 YELLOW 42
- 3. RHR Subsystems Available (0, 11 or 2) ;::5 5 GREEN
- 4. RCS levellevel;;:: 126' 126 6"6 . Defueled)
(GREEN ififDefueled)
- 5. Time to saturation>
saturation > 30 minutes OR RCS press press>> 325 psig with at least one RCP available for operation and at least one SG available Core Cooling Subtotal POWER AVAILABILITY A V AILABILITY Subtotal Condition AOP 1.
- l. 11 "A"A Train DG Available 0-2 RED 43
- 2. 11 "B"B Train DGDO Available 33 ORANGE 43 45 4-5 YELLOW 43
- 3. F 4160 V BUS normal (Aligned to A SUT) 66 GREEN
- 4. G 4160 V BUS normal (Aligned to B SUT)
- 5. 2 Feeds available to the HV Switchyard (0, 11 or 2)
Power Availability Subtotal CONTAINMENT Subtotal Condition AOP 1.
- l. Refueling Integrity Set 0-1 RED 44
- 2. CTMT Closure Set 2-4 ORANGE 44
- 3. No Core Alterations in Progress (2 pts) 5-6 YELLOW 44 7 GREEN
- 4. Equipment Hatch & Air Locks Closed or Capable of Being Closed on Short Notice if Defueled)
(GREEN ifDefueled)
- 5. level 126' RCS level;;:: 126 6" 6 (3 pts)
Containment Subtotal INVENTORY Subtotal Condition AOP 1.
- l. RefuelingCavity23 Refueling Feet(142l)AboveFuel Cavity;;:: 23 Feet (142' I") Above Fuel 0 RED 45
- 2. LHSI Pump/Flowpath Available I ORANGE 45 HHSI Pump/Flowpath Available 2 YELLOW 45 3.
3-4 GREEN
- 4. RCS is Intact below the Reactor Vessel Flange if Defueled)
(GREEN ifDefueled) Inventory Subtotal InventOl'y RCS INTEGRITY Subtotal Condition AOP 1.
- l. All S/G Manways or Nozzle Dams Installed 0-1 ORANGE 46
- 2. RCS is Intact below the Reactor Vessel Flange 2 YELLOW 46
- 3. Pressurizer level < 100% 3 GREEN (GREEN ifDefueled) if Defueled)
RCS Integrity Subtotal SPENT FUEL COOLING Subtotal Condition AOP l.
- 1. SFP level;;::
level 23 feet (151 (1516)
'6") above fuel (4 pts) 0-4 RED 47
- 2. A Trn Tm SFP Cooling available 5 ORANGE 47 B Trn Tm SFP Cooling available 6 YELLOW 47 3.
7 GREEN
- 4. ;;:: 2 SFP Makeup Sources (RWST, DW, RMW to Blender, Boric Acid to Blender, RHT to transfer canal with weir gate removed)
SFP Subtotal Time to saturation JE IF core cooling were lost: hours minutes Page 6 of 18 Version 36.0
11/13/09 12:03:44 11113/09 - FNP-0-UOP-4.0 APPENDIX 11 FIGURE IB lB SHUTDOWN SAFETY ASSESSMENT (Mode 4) Unit: _ _ Prepared By: _ _ _ _ _ _ _ Date: _ _ _ _Time:___ By:_______________ Time:______ App-i, Fig 2 Evaluated App-l, LI 0 SHUTDOWN SAFETY FUNCTION! FUNCTIONI CRITERIA CONDITION (Circle Condition) (No!False0, Yes/True= (NolFalse=O, Yes/Truel, 1 Use number within range when required) REACTIVITY Subtotal Condition AOP l.
- 1. No positive reactivity changes in Progress --- 0-1 RED 41
- 2. Number of Boration Flow Paths (0, 1,2) 1, 2) (Ref step 2.13) --- 2 ORANGE 41
- 3. RCS Boron: CSD boron concentration --- 3-4 YELLOW 41
- 4. Number of Source Range Instrumentation Available --- 55 GREEN Reactivity Subtotal ---
CORE COOLING Subtotal Condition AOP 1.
- l. 2 SGs Available (2 pts if~ S/G's Available (Ref step 2.7) if 2 S/Gs --- 0-1 RED 42
- 2. RHR Subsystems Available (0, 11 or 2) --- 2-3 ORANGE 42
- 3. PRZ level within normal operating band --- 4 YELLOW 42
- 4. Margin > 16° F RCS Subcooling Margin> --- ~5 GREEN Core Cooling Subtotal POWER AVAILABILITY A V AILABILITY Subtotal Condition AOP 1.
- l. 11 "A" A Train DG Available --- 0-2 RED 43
- 2. 11 "B" B Train DG Available --- 33 ORANGE 43
- 3. F 4160 V BUS normal (Aligned to A SUT) 4-5 YELLOW 43
- 4. G 4160 V BUS normal (Aligned to B SUT) 6 GREEN
- 5. 2 Feeds available to the HV Switchyard (0, 11 or 2) ---
Power Availability Subtotal --- CONTAINMENT Subtotal Condition AOP 1.
- l. CTMT Integrity meets tech spec requirements 0-1 RED 44
- 2. RCS borated to cold shutdown boron concentration (2 pts) 2-4 ORANGE 44
- 3. CTMT Cooling tech spec are met (3 pts) --- 5-6 YELLOW 44 Containment Subtotal 6 GREEN INVENTORY Subtotal Condition AOP 1.
- l. PRZ level within normal operating band --- 0 RED 45
- 2. Pump!Flowpath Available LHSI Pump/Flowpath --- I1 ORANGE 45
- 3. HHSI Pump/Flowpath Pump!Flowpath Available 2 YELLOW 45
- 4. Normal make-up capability available 3-4 GREEN Inventory Subtotal RCS INTEGRITY Subtotal Condition AOP 1.
- l. LTOP L TOP TECH SPEC MET --- 0-1 ORANGE 46
- 2. RCS/PRZ cooldown rate < tech spec allowable RCS!PRZ --- 2 YELLOW 46
- 3. Pressurizer operable per tech specs --- 33 GREEN RCS Integrity Subtotal SPENT FUEL COOLING Subtotal Condition 1.
- l. SFP level ~ 23 feet (151 (1516)
'6") above fuel (4 pts) --- 0-4 RED 47
- 2. Tm SFP Cooling A Trn --- 55 ORANGE 47
- 3. Tm SFP Cooling B Trn --- 6 YELLOW 47 4 ~ 2 SFP Makeup Sources (RWST, DW, RMW to Blender, Boric --- 7 GREEN Acid to Blender, RHT to transfer canal with weir gate removed)
SFP Subtotal Page 7 of 18 Version 36.0
11113/09 12:03:44 11/13/09 12:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX 11 Figure Figure 22 Yellow/Orange Condition Signs Required for Single Train Train Availability
- 1. IF required by step 4.6, THEN place caution signs at applicable location specified in Table 22 for Unit 11 or Table 33 for Unit 2.
- 2. Signs should be worded similar to the following:
TRAIN OUTAGE OUT AG E IN PROGRESS NO WORK IS TO BE DONE ON THE TRAIN C.ALL EXT. CALL
- 3. Complete Table 2 or 33 to document the review of posting requirements.
3.1 Mark as N/ N/A A any components which are not required to be posted for the given yellow or orange condition. 3.2 Post signs at the applicable locations and initial the appropriate block of Table 2 or 3. 3.3 When the yellow/orange condition no longer exists, ensure the signs have been removed and initial the appropriate block of Table 2 or 3. Page 80f18 8 of 18 Version 36.0
11113/09 12:03:44 11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 11 TABLE I1 Safety Assessment Required for Voluntary Entry to a Shutdown Safety Contingency Actions Required Orange or Yellow condition. Orange Condition Contingency Actions for Entry Reactivity Orange Condition 1.
- 1. Voluntary entry into a Reactivity Orange condition is not anticipated.
Reactivity Yellow Condition Contingency Actions for Entry
- 1. Verify Technical Specification and Technical Requirements Manual requirements are met and will continue to be met for boron concentration, boration flow path, and source range instrumentation.
Page 9 of 18 Version 36.0
11/13/09 12:03:44 11113/09 FNP-0-UOP-4.0 APPENDIX 11 TABLE 11 Contingency Actions Required for Voluntary Entry to a Shutdown Safety Assessment Orange or Yellow condition. Core Cooling Orange Condition Contingency Actions for Entry NOTE: Voluntary entry into a core cooling Orange condition is not normally foreseen for evolutions other than Mid Loop Operations or other reduced inventory evolutions (e.g. drain down for reactor vessel head lift). Under certain plant min., an orange condition may be saturation::;; 30 mm., conditions with time to saturation encountered.
- 1. IF Orange condition entry is being made as part of Mid Loop Operations, THEN ensure of FNP-1-UOP-4.3 OR FNP-2-UOP-4.3, MID LOOP OPERATIONS, the requirements ofFNP-I-UOP-4.3 have been met, including the Mid-Loop Compensatory measures in Appendix 33 of FNP-1-UOP-4.1 FNP-2-UOP-4.1, CONTROLLING PROCEDURE FOR FNP-I-UOP-4.l OR FNP-2-UOP-4.l, REFUELING.
- 2. IF orange condition entry is due to certain plant conditions, with time to saturation
- 30 minutes, THEN ensure the contingency actions specified in the memo for compensatory measures for RCS level at the reactor vessel flange as required by of FNP-1-UOP-4.1 OR FNP-2-UOP-4.1, CONTROLLING PROCEDURE Appendix 33 ofFNP-I-UOP-4.1 FOR REFUELING, have been met. These same contingency actions are applicable for non-refueling outages when RCS level is at the reactor vessel flange in these conditions.
Core Cooling Yellow Condition Contingency Actions for Entry
- 1. Ensure both trains of RHR are operable if in Mode 6 prior to lowering refueling cavity level to < <23 (142l) 23 feet (142' 1") above the fuel.
of 18 Page 10 of18 Version 36.0
11/13/09 12:03:44 11113/09 FNP-0-UOP-4.0 APPENDIX 11 TABLE 11 Contingency Actions Required for Voluntary Entry to a Shutdown Safety Assessment Orange or Yellow condition. Power Availability Orange Condition Contingency Actions For Entry
- 1. Verify RCS level ~ 126' 6 prior to voluntary Orange condition entry.
126 6"
- 2. Refer to Technical Specification 3.8.2.
- 3. Based on the unit outage, as a minimum, ensure the Unit 11 or Unit 2 F OR G 4160V Bus is maintained with:
- An offsite power feed through its associated startup transformer.
- Its associated DG(s) operable
- An operable charging pump in the boration flow path
- An operable BABATP BATP TP if a BA TP is required as part of the boration flow path
- An operable RWST TO CHG PUMP SUCT MOV if the RWST is part of the boration flow path
- An operable RHR, CCW, and SW Pump
- 4. IF the head is on the reactor vessel, THEN at least one PRZR PORV is operable with backup nitrogen available for use in feed and spill cooling in the event that RHR is lost.
Notify the Shift Manager, Alabama Control Center (ACC), or outside SO as appropriate to ensure that no work is in progress that could adversely affect the operable train of AC power and to ensure that no such work is started while this Orange condition exists.
- 5. Ensure that no work is in progress in the low voltage switchyard that could adversely affect the operable train of AC power.
- 6. Notify EM supervisory personnel of AC power conditions and requirements and direct their personnel (including appropriate Williams and EFS personnel) be briefed on these conditions and requirements.
- 7. Install Caution Tags or place barricades as appropriate to identify components such as ESF bus feeder breaker, DGs, DG output breakers and bus tie breakers, and startup transformer associated with the ESF bus to be maintained operable.
Page 11 of 18 Version 36.0
11113/09 12:03:44 11/13/09 12:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 11 TABLE TABLE 11 Contingency Actions Contingency Required for Voluntary Actions Required Voluntary Entry to aa Shutdown Entry to Safety Assessment Shutdown Safety Assessment Orange or Orange Yellow condition. or Yellow condition. Condition Contingency Actions For Entry Power Availability Yellow Condition 1.
- 1. Verify RCS level ~ 126 6" prior to voluntary Yellow condition entry.
126' 6
- 2. Refer to Technical Specification 3.8.2.
- 3. Based on the unit outage, as a minimum, ensure the Unit 11 or Unit 2 F OR G 4160V Bus is maintained with:
- An offsite power feed through its associated startup transformer.
- Its associated DG(s) operable
- An operable charging pump in the boration flow path
- An operable BATP if a BATPBATP is required as part of the boration flow path
- An operable RWST TO CHG PUMP SUCT MOV if the RWST is part of the boration flow path
- An operable RHR, CCW, and SW Pump
- 4. IF the head is on the reactor vessel, THEN at least one PRZR PORV is operable with backup nitrogen available for use in feed and spill cooling in the event that RHR is lost.
- 5. Ensure that no work is in progress in the low voltage switchyard that could adversely affect the operable train of AC power.
- 6. Notify EM supervisory personnel of AC power conditions and requirements and direct their personnel (including appropriate Williams and EFS personnel) be briefed on these conditions and requirements.
12 of 18 Page 120f18 Version 36.0
11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 1 TABLE 1 1 Contingency Actions Required for Voluntary Entry to a Shutdown Safety Assessment Orange or Yellow condition. Containment Orange Condition Contingency Actions For Entry
- 1. Verify no core alterations in progress or planned.
- 2. IF Orange condition entry is being made as part of Mid Loop Operations, THEN base on the unit outage ensure the requirements of FNP-1UOP-4.3 OR FNP-2-UOP-4.3, MID ofFNP-I-UOP-4.3 LOOP OPERATIONS, have been met.
Containment Yellow Condition Contingency Actions For Entry
- 1. Not applicable.
Page 13 of 18 Version 36.0
11/13/09 12:03:44 11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 11 TABLE 11 Contingency Actions Required for Voluntary Entry to a Shutdown Safety Assessment Orange or Yellow condition. Inventory Orange Condition Contingency Actions For Entry
- 1. Voluntary entry into an Inventory Orange condition is not anticipated.
Inventory Yellow Condition Contingency Actions For Entry
- 1. Ensure both trains ofRHR <23 of RHR are operable before reducing refueling cavity level to < 23 feet above fuel.
- 2. IF entry is due to Mid Loop Operations, THEN based on the unit outage, ensure the requirements ofFNP-I-UOP-4.3 of FNP-1-UOP-4.3 OR FNP-2-UOP-4.3, have been met.
- 3. Refer to applicable Technical Specifications before removing RHR or HHSI systems from service.
Page 14 14 of 18 Version 36.0
11/13/09 12:03:44 11113/09 FNP-0-UOP-4.0 APPENDIX 11 TABLE 11 Contingency Actions Required for Voluntary Entry to a Shutdown Safety Assessment Orange or Yellow condition. RCS Integrity Orange Condition Contingency Actions For Entry
- 1. IF entry is due to Mid Loop Operations, THEN based on the unit outage ensure the of FNP-1-UOP-4.3 OR FNP-2-UOP-4.3, MID LOOP OPERATIONS, have requirements ofFNP-I-UOP-4.3 been met.
- 2. WHEN SO SG cold leg manways are to be opened OR cold leg nozzle dams are to be removed, THEN verify that at least one hot leg manway, diaphragm, and nozzle dam has been previously removed.
RCS Integrity Yellow Condition Contingency Actions For Entry
- 1. IF entry is due to Mid Loop Operations, THEN based on the unit outage ensure the requirements ofFNP-I-UOP-4.3 of FNP-1-UOP-4.3 OR FNP-2-UOP-4.3, MID LOOP OPERATIONS, have been met.
- 2. WHEN SO SG cold leg manways are to be opened OR cold leg nozzle dams are to be removed, THEN verify that at least one hot leg manway, diaphragm, and nozzle dam has been previously removed.
Page 15 of 18 Version 36.0
11/13/09 12:03:44 11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 11 TABLE 11 Voluntary Entry to a Shutdown Required for Voluntary Contingency Actions Required Safety Assessment Shutdown Safety Orange or Yellow condition. Orange Spent Fuel Cooling Orange Condition Contingency Actions for Entry
- 1. Voluntary entry into an Orange condition is not anticipated.
Spent Fuel Cooling Yellow Condition Contingency Actions for Entry
- 1. Verify that at least one train of SFP cooling and at least one makeup source are maintained operable.
- 2. Ensure that operating train SFP HX outlet temperature is being monitored every four hours on Rad Side SO logs.
Page 16 of 18 Version 36.0
11/13/09 12:03:44 11113/09 FNP-0-UOP-4.0 APPENDIX 11 TABLE 2 Protected Train Postings Unit 11 Components Sign Posted Sign Removed Initials Initials Charging Pump lA1A (B,C) RHR Pump lA 1A (B) CCW Pump lA 1A (B,C) BATP lA1A (B) Diesel Generator 1-2A (lC, (1C, 2C, IB, 2B) SFP Cooling lA 1A TRN (B TRN) 4160 V Buses F and K (Buses G and L) Aux Bldg DC Swgr, A TRN (B TRN) Aux Bldg Battery, A TRN (B TRN) SW Pumps lA 1A (B, C, D, E) SW Valve Boxes 1A, or IB Start Up Transformers lA, lB Other Page 17 of 18 Version 36.0
11113/09 11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 11 TABLE 3 Protected Train Po stings Unit 2 Postings Components Sign Posted Sign Removed Initials Initials Charging Pump 2 (B,C) RHR Pump 2 (B) CCW Pump 2 (B,C) BATP 2 (B) Diesel Generator 1-2A (1 C, 2C, or 2B (1C, 2B)) SFP Cooling A TRN (B TRN) 4160 V Buses F and K (Buses G and L) Aux Bldg DC Swgr, A TRN (B TRN) Aux Bldg Battery, A TRN (B TRN) SW Pumps 2A (B,(B, C, D, E) SW Valve Boxes Start Up Transformers 2A or 2B Other Page 18 of 18 Version 36.0
T-33 ADMIN HLT-33 FNP HL 1 of 7 Page 1 001A4.11- RO & A.2.1.A Equipment Control ADMIN -OOlA4.11- & SRO A.2.1.A TITLE: Perform A Shutdown Margin Calculation in modes 11 & & 2. PROGRAM APPLICABLE: SOT SOCT____ OLT ~ SOCT LOCT____ X LOCT __ ACCEPTABLE EVALUATION METHOD: ~ X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM --.2L X CLASSROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: N/A NIA ALTERNATE PATH TIME CRITICAL PRA. __ PRA_____ JPM DIRECTIONS:
- 1. Initiation of task may be in group setting; evaluation performed individually upon completion of the task by reviewing the completed form.
- 2. Provide the examinee with the required materials to perform this JPM.
TASK STANDARD:
- Perform a Shutdown Margin calculation while in Mode 1, using STP-29.5 accurately to within elements standard.
the acceptable ranges identified within each critical element's
- Identify the need to emergency borate.
Examinee: 1PM Performance: Overall JPM Satisfactory 0 Unsatisfactory V nsatisfactory 0D Evaluator Comments (attach additional sheets if necessary) EXAMINER: _________________ Developer H. Fitzwater 10/28/09 NRC Approval SEE NUREG 1021 FORM ES-301-3ES-3013
FNP HL T-33 ADMIN HLT-33 A.2.1 .A A.2.1.A Page 2 of 7 CONDITIONS When I tell you to begin, you are to Determine the excess Shutdown Margin using STP-29.5, SHUTDOWN MARGIN CALCULATION IN MODES 11 AND 2 (TA VG 2: 547°F), for Unit 1. The (TAVG conditions under which this task is to be performed are:
- a. Unit 11 is stable at 90% with the ramp on hold
- b. Bank D indicates 192 by Group Demand.
- c. Seven of the Bank D rods (H2, B8, H14, F6, FlO, KI0, Kb, K6) are at 192 steps by DRPI.
- d. Rod P8, in the D bank, has been determined to be stuck.
- e. Rod P8 is at 162 steps by DRPI.
- f. All other rods are at 229 steps.
- g. MWD/MTU burnup.
Core burnup is 9,800 MWDIMTU
- h. FNP-1-STP-29.5, SHUTDOWN MARGIN CALCULATION IN MODES 11 AND 2 (TAVG2:
FNP-I-STP-29.5, (TAVG? 547°F), initial conditions are satisfied. i.
- 1. FNP-1-STP-29.5 starting at step 5.1 and identify The Shift Supervisor has directed you to complete FNP-I-STP-29.5 whether or not emergency boration is required.
INITIATING CUE: You may begin.
"You begin."
EVALUATION EV ALUA TION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME NOTE: Elements 11 through l3 13 are evaluated by comparing the completed Calculation page to the values and ranges acceptable ran es of each element. The acce responses table res onses are ALSO listed on the calculation KEY.
- 1. Step A.1: Document Core Burnup 1) Value entered: 9,800 MWD S I/ U S
- 2. Step A.2: Document Power Level 2) Value entered: 90 %
% entered S I/ U S
FNP HLT-33 ADMIN A.2.1 .A A.2.1.A Page 3 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE)
- 3. Step A.3: Determine penalty steps for Banks 3) Value entered: ZERO (0) S I/ U S
below RIL. (RNG: NONE) a) Using COLR figure 11 determines RIL (a). Determines RIL from COLR for 90% power level. . CB DID/ RIL = 167 (165-170) from COLR.
- CBC I RIL = FULL OUT CBC/RJL=FULL (or 229).
b) Gathers data from Conditions page Documents given Demand (b).Documents (b). positions
- CB DI D/ Demand 192.
- All others: Full out (or c) Determines penalty steps per bank. 229)
(c). Calculates difference
- All values: 0 (RNG: NONE)
** 4. Step A.4: Determine number of penalty steps 4) Value entered: 5 S I U S
for RODS below RIL (RNG: 3-8) a) Determines stuck rod in CBD, Determines CBD RIL.ML. (a). Determines RIL from COLR
- P8 -7 CB DI RIL = 167 P8CBDIRIL=167 (Range: 165-170) from b) Documents given Data for rod P-8 COLR.
(b). Documents given data i.I. Rod # -7 P8 @ 162 Rod#-)P8@162 c) Calculates difference (c). Calculates difference (ML - DRPI) = 5 (RNG: 3-8) (RIL
** B.1: Determine Rod Worth for all
- 5. Step B.l: 5) Value entered: 6268 pcm. S I/ U control and shutdown bands at Zero steps (range: NONE) using given power and burnup:
a) Uses Curve 77 pg 11 for 90% power I0000MWD and 10000MWD
- 6. Step B.2: Calculate penalty value of rod banks 6) Value entered of 0 (zero) pcm S I U
- 7. Step B.3: Calculate penalty value of individual 7) Value entered of 50 pcm S I/ U S
rods (range: 30-80)
HL T-33 ADMIN FNP HLT-33 A.2.1 .A A.2.1.A Page 4 of 77 EVALUA nON CHECKLIST EVALUATION RESULTS: ELEMENTS: STANDARDS: (CIRCLE) (CIRCLE)
- 8. Step B.4.a; Determine most reactive Rod 8) Value entered of 1406 pcm SS / U worth (range: NONE)
(a). From Curve 77 pg 22 for for.:S 0000MWD. 110000MWD.
** 9. Step B.4.b; Calculate rod worth of 9) Value entered of of3515 3515 5S I/ U U
stuck/untrippable rod (RNG: 3515- 3516) (a). ## of stuck: 11 rod BA.a: 1406. (b). B.4.a: (+1 (+ 1 / -0) value for various rounding technique effects)
- 10. Step B.5; Calculate penalized rod worth 10) Value entered of: S / U S
(-) 2432.7 NOTE: NEG (-) (-) SIGN IS IMPORTANT FOR THIS CALCULATIONlEvaiuation CALCULATION/Evaluation (RNG: (-)2403 to (-) (-) 2451 2451)) Transpose data from other steps: B.1: 6268 (a). B.l: (b). B.2: 0 (c). B.3: 50 (d). B.4.b BA.b 3515. Calculate using equation.
- 11. Step B.6; Determine power defect for given 11) Value entered of: S / U conditions 1634 pcm (RNG: NONE)
(a). From Curve 78 for.:S for < 1 0000MWD. 10000MWD.
HLT-33 FNP HL T-33 ADMIN A.2.1 .A A.2.1.A Page 5 of 7 EVALUATION EV ALUA nON CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE)
** 12. Step B.8; Calculate available Shutdown 12) Value entered of: S S / U Reactivity (-) 748.7
(-) (RNG: -718 to -767) NOTE: NEG (-) (-) SIGN IS IMPORTANT FOR THIS CALCULATIONlEva/uation CALCULATION/Evaluation (a). Transpose data:
- i. (-) 2432.7 B.5: (-)
ii. B.6: 1634 iii. Calculate
** 13. Step B.9; Calculate Excess Shutdown Margin 13) Value entered of: S / U S
(+) (+) 1021.3 (RNG: 1003 to 1051) NOTE: POS (+) (+) SIGN IS IMPORTANT IMPOR TANT FOR THIS CALCULATIONlEva/uation CALCULATION/Evaluation (a). Transpose data:
- i. B.8: (-)
(-) 748.7 ii. Calculate NOTE: Element 15 is not required to be completed but is likely to be completed/initialed if initiated as a group/classroom setting.. rou /classroom settin
- 14. Step B.10: Identifies Need to Emergency 14) Notifies Shift Supervisor of S / U S
Borate need to Emergency Borate.
- 15. completes task: 15) Completes sign off. S / U a) Signs and dates Calculation Sheet (a). Signs and dates form b) Initials step 5.1 (b).Initials (b ).Initials step 5.1 of procedure.
c) Asks for verification of calculation I TERMINATE After calculation of Excess Shutdown Margin AND element 14 completed. STOP TIME CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) (*) before the element number.
FNP HLT-33 FNP HL T-33 ADMIN ADMIN A.2.1 .A A.2.1.A Page of 77 Page 66 of GENERAL
REFERENCES:
GENERAL
REFERENCES:
FNP-l-STP-29.5, VER4.0
- 1. FNP-1-STP-29.5,
- 1. VER 4.0
- 2. KA: 001A4.11 2.KA:001A4.11 RO 3.5 3.5 SRO SRO 4.1 GENERAL TOOLS AND EQUIPMENT:
EQUIPMENT: 1.
- 1. FNP-l-STP-29.5, ver FNP-1-STP-29.5, ver 4.0 4.0
- 2. PCB-VOL1-CRV77, Cycle 23 rev 88
- 3. PCB-VOL1-CRV78, Cycle 23 rev 88
- 4. 1, COLR for FNP Uniti Unit 1, Unitl Cycle 23, Rev 00 Figure 1.
1.
- 5. Pen/Pencil
- 6. calculator Critical ELEMENT justification:
STEP Evaluation 4-13 CRITICAL - Calculation completion; each step is critical in accurately determining available SDM and Excess SDM. 14 CRITICAL - Task Objective; Identification that Acceptance Criteria NOT met and Emergency boration IS required to ensure corrective action is initiated and compliance with T.S. is restored. COMMENTS:
KEY A. PRESENT CONDITIONS A.l A.1 Core Burnup 1980019_80_0____IMWD/MTU A.2 Power Level. 190 190 II %
°° A.3 Determine number of penalty steps for ROD BANKS below RIL.
(Use COLR or convert the RIL computer reading from % to steps) A.3.a Record data in table ROD BANKRIL BANK RIL BANK STEPS BELOW BANKS HEIGHT DEMAND RIL_ RIL ,...- CBA FULL OUT Full Out (229) 0 CBB HTn T flTTT 17TTTT nTTT Full Out (229) 0 CBC Full Out(229) - Full Out (229) 0 CBD CBD 167 167 (166-170) - 192 0 SDA FULL gUI UUl Full Out (229) 0 SDB FULL OUT Full Out (229) 0 TOTAL STEPS BELOW RIL : _------_ I I ° I..: II RANGE for CBD RIL: LO: Readability of COLR RIL curve may allow allow as low as 165 steps; although this is <<than than the curve limit of 166.9, if calculated. The assumptions within the curve development provides for this readability error. HI: conservatism allowed by P&L 4.1 may maybebe instituted and a value of up to 170 steps may be selected since the specific value between the Y-axis increments may not be calculated. 1 of3 Page lof3 Revision 4
KEY A.4 Determine number ot penalty steps tor RODS below ML which were not counted in A.3 (Rods below RIL on DRPI when the BANK demand is above RIL) (Use COLR or convert the RIL computer reading from % to steps) AA.a Record data in table A.4.a ROD NUMBER RIL POSITION POSITION DRPI POSITION DIFFERENCE
~ P8 167 (+3,-2) 162 55 (3-8) j~
I 5 Ii TOTAL STEPS BELOW RIL I5 I 1....- I (RANGE 3-8) I I.... B. SHUTDOWN MARGIN NOTE: Write the values from Curves 77 & 78 directly into the surveillance test. The correct sign convention has been entered in the STP. B.1 Rod worth for all control and shutdown banks at zero steps at Present Burnup (A. Present 1) and Power Level (A.2) (A.1) (A.2).. : ~_~ 1r--6-2-68-...... 16268 1lp:~ pcm -: Ii (Curve 77 Page 1) I 1... _ _ _ _ _ _ _ _ _ _ .. L B.2 Penalty value of rod banks below insertion limit:
~
I 0 steps x 75 pcm/step = CJ.: :i (A.3.a) (A.3 .a) B.3 Penalty value of individual rods below RIL which were not counted in A.3 r--~oII.I.loO""""~ fPr1c Iir RILRIL on DRPI when the BANK demand is above RIL) 5 r------------ IS (NGE 3-8)_L (RANGE 3-8) s x 10 pcm/step = r I I L (+)j (+) 50
- (RNG 1cm em:
_______ - - - J 30-80) (A.4.a) of 3 Page 2 of3 Revision 4
1.* * *. *~0:*
~; : KEY B.4 Stuck /I Untrippable Rod penalty:
zero (B.4.a is N/A and B.4.b is zero if there are no stuck/untrippable (B.4.a stuck/untrippable rods) B.4.a Worth of most reactive rod worth at present burnup (A.l) (A.1) (_)j1406 (-)J 1406 Ipcm Ipcm from Curve 77 pg. 2 B.4.b Calculate worth of Stuck/untrippable Stuckluntrippable rods [fl 1 (# Stuck! Stucki x (-)~ ()1 11406 I (B.4.a) k 1.75] + [()
+ [(_)1 (B.4.a) 1406 I I x 0.75]
0 75] =
= (_) 5153S1S lange.
range: 515 516 3S1S to i3S16 1 [-2460.5 to -2461] untripp + [ -1054.5 to -1055] = B.5 Penalized rdu I [3515 0R3516] VUL111 U111U1111 LULrsJUii1LIppauIc LUU, misaligned rods, rods below the insertion limit, and uncertainty: 50 3515 3S1S -------.-., 2432.7 range: 6268 0 1 (-)2432.7range: (-) 1
+ + 30 - 80 (_),..!!!(~+l~,-~O)!!!!!I
(+1, ) x 0.9 = ( ) -2403 to-2451 1 ( ) 1 to -24S1 n 1 L _ -'-_ _ _ _......[ill L- [6268÷80+35I5J*0.9 2405.7 (B.4.b) [-6268+80+3517] *09 = 2403.9 (Round down to 2403)*LO [6268+30+35 15] *0.9 = 2450.7 (Round up to 2451) *(bi) [-6268+30+3517] *0 9= 24489 md Burnup (A.1)
=IU 1634 (Curve 78). (-)
() 1 pcm Ipcm B.7 Void Collapse Defect. (+) 50 pcm B.8 Available Shutdown Reactivity: (-) 748.7 (-)748.7 - -, ( )I ()1-2432.7 l- (_)---1.1_163_4 [__) I 11634 _ _ ++ 50 Range:
-719 to -767.0 pcmi pcml 1
(B.5) (B.6) (B.7) B.9 Shutdown Margin in excess of required Shutdown Margin (B.8 - Required SDM from the COLR): 1-748.7 1,-748.7 a~-==~_pcm (1, I pcm -()(-) 1770 pcm = r - - - - - - - - - - -I 1 ( (+) 102l.3 Icm r.m 1I 1 Range: 1003 v (B.8) Required SDM 1 to 10S1 tolO5l I 1..._ ....._ _ _...... from the COLR 3 1021 I(+) B.l0 B.IO If B.9 is positive, THEN emergency borate per FNP-I-AOP-27.0, IfB.9 FNP-1-AOP-27.0, EMERGENCY Emergency Boration BORATION, to establish the required shutdown margin otherwise Shutdown IS required Margin is adequate for the Present plant condition. DATE-- Element IS-if 15-if 15- if assumes/states Signed-- element IS-May also state that a assumes/states Performed by: _ Emerg Boration completed Rx trip may be warranted (P&L 4.3). emergency boration completed Verified Verified by: by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Page 3 of3 of 3 Revision 4
Westinghouse Westinghous e Proprietary Class22 ProprietaryClass PCB-1-VOL 1-CRV77 PCB-l-VOLl-CRV77 UNIT 11CYCLE UNIT CYCLE 23 CURVE 77 23 CURVE 77 KEY /1 REV.~ REV. APPROVED:: APPROVED t)(~., AA: f<4f 2L f~r P"'rt1~ t'7'-_H<!Y 1fI# ENGINEERING ENGINEERI SUPPORT MANAGER NG SUPPORT MANAGER DATE DATE ARI-l Rod ARI-1 Rod Worth Worth (pcm)(pern) forfor Shutdown Shutdown Margin Margin Calculations Calculations BumupRange Burnup Range Power Level Power Level (%) (%) (MWD/MTU)) (MWD/MTU 00 10 10 20 20 30 30 40 40 50 50 60 60 70 70 80 80 90 90 100 100
~150 150 4587 4587 4710 4710 4831 4831 5071 5071 5311 5311 5483 5483 5655 5655 5792 5792 5927 I 6162 5927 6162 6397 6397
> 150
> 150 ~1000 1000 4667 4667 4801 4801 4935 4935 5180 5180 5425 5425 5594 5594 5762 5762 5905 5905 6048 6048 6285 6285 6523 6523
> 1000
>1000 ~2000 2000 4717 4717 4867 4867 5017 5017 5267 5267 5517 5517 5680 5680 5844 5844 5995 5995 6145 6145 6384 6384 6623 6623
> 2000
> 2000 ~3000 3000 4755 4909 5063 5320 5320 5578 5578 5740 5740 5902 5902 6052 6201 6442 1 6683 6683
> 3000
> 3000 ~4000 4000 4818 4818 4975 4975 5131 5131 5396 5396 5660 5660 5814 5969 5969 6113 6257 6257 6483 6483 6708 6708
>4000
> 4000 ~5000 5000 4767 4920 5072 5346 5619 5778 5938 6073 6208 6439 6670 6670
> 5000
> 5000 ~6000 6000 4717 4865 5013 5296 5579 5743 5906 6033 6159 6395 6631 6631
> 6000
>6000 ~7000 7000 4689 4827 4965 5254 5254 5542 5714 5714 5885 6001 6118 6355 6593
> 7000 7000 ~8000 8000 4660 4788 4916 5211 5506 5685 5864 5 Element #6 6316 6555
> 51
< <)000 ~ 5669 5857 54 5 6292 6531 6531
'> ROOO 800QQ 0. ~- -~ ~ 4 5182 ~L 5480 w 62~
~;m;_
4632 4742 4852 5154 5455 5652 5850 5939 6028 6268 6507 I > 9000
> 9000 ~10000 10000
>10000 4622 4725 4828 5129~ . 5431
~'5r3"l *~61J.
564f 5!SSO-5850 -5'9~3 5933 -6IJi6- 6016 -625:6253J 6490
>10000 ~11000 11000 4828 5129
>11000
>11000 ~12000 12000 4612 4707 4803 5105 5408 5629 5850 5927 6004 6239 6239 6473 6473
>12000
>12000 ~13000 13000 4617 4706 4795 5096 5398 5631 5865 5937 6010 6242 6475 6475
>13000
>13000 ~14000 14000 4621 4704 4787 5087 5387 5633 5879 5947 6015 6245 6476 6476
>14000
>14000 ~15000 15000 4631 4709 4787 5086 5385 5642 5900 5964 6028 6256 6485 6485
>15000
>15000 16000 ~16000 4641 4714 4787 5085 5382 5652 5921 5981 6041 6267 6493 6493
>16000
>16000 ~17000 17000 4662 4731 4731 4800 5096 5096 5391 5391 5669 5669 5947 5947 6004 6004 6062 6062 6286 6286 6510 6510
>17000
>17000 18000 ~18000 4682 4748 4813 5107 5107 5400 5687 5973 6028 6083 6304 6526 6526
>18000
>18000 ~19000 19000 4709 4709 4771 4771 4833 4833 5125 5125 5418 5418 5710 5710 6002 6002 6056 6056 6109 6109 6328 6328 6547 6547
>19000
>19000 ~20000 20000 4735 4735 4794 4794 4852 4852 5144 5144 5435 5435 5734 5734 6032 6032 6083 6083 6135 6135 6351 6351 6568 6568
>20000
>20000 ~20885 20885 4760 4760 4818 4818 4876 4876 5165 5165 5454 5454 5759 5759 6063 6063 6112 6112 6161 I 6377 6161 6377 6592 6592 Notes:
Notes: 1.1. Rod Rod worth worth data data assumes assumes the the starting starting point point isis rods rods at at the the Rod Rod Insertion Insertion Limit. bank isis below Limit. IfIf aa bank below the RIL, reduce the RIL, the reduce the table value table value by by 75 75 pcm pcm for for each each step step below below the the RIL. RIL. 2.2. The The rod rod worth worth data data represents represents negative negative reactivity. reactivity. However, However, STP-29.1, STP-29.2 and STP-29.1, STP-29.2 and STP-29.5 STP-29.5 have been written have been to written to handle handle the the correct correct sign sign convention convention when when thethe above above data data isis entered entered as a positive number. Enter the above as a positive number. Enter the above numbers numbers directly directly into into the the STP. STP. 3.3. ARI-1 ARI-1 isis defined defined as as All All Rods Rods InIn --less
-- less the the most most reactive reactive rod.
rod. The SDM calculation The SDM that one requires that calculation requires rod be one rod assumed be assumed stuck. stuck. Therefore, Therefore, use use the the data data directly directly from from the the table table above above when when there there are are not not any any known known stuck stuck rods. rods. of 2 Page 11 of2 Page
Westinghouse Proprietary Westinghouse Class 22 Proprietary Class PCB-1-VOL1-CRV77 PCB-l-VOLI-CRV77 UNIT 11 CYCLE UNIT CYCLE 23 23 CURVE CURVE 77 77 Control Rod Control Rod Worth Worth for for SDM Calculations SDM Calculations I REV. REV. 8 KEY
- /#
APPROVED: APPROVED: y~ k. f4 IN Btyr
;cr ptr"" (n (1'-;,1<"- Lf-!5-(!1 ENGINEERING SUPPORT ENGINEERING SUPPORT MANAGER DATE DATE Worth of Worth of Most Reactive Rod Rod (pcm) for Shutdown Shutdown Margin Calculations BumupRange Burnup Range Power Level Power Level (MWD/MTU) 0%
0% to to 100% 100%
- 150 150 658
> 150 150 ::;;1000 l000 676
> 1000
>1000 ::;;2000 2000 732
> 2000
>2000 ::;;3000 3000 781
>3000 ::;;4000 4000 889
>4000 ::;;
50005000 1024
> 5000 ::;;6000 6000 1160
> 6000 ::;;7000 7000 1232
> 7000
>7000 <8000 8000 1304 Ielement #9 ]I > 8000
>8000 ::;;9000 9000 1355 I >
> 9000
>10000
- 10000 10000
- 11000 11000 -
1406 1450 I
>11000 ::;;12000 12000 1494
>12000 ::;;13000 13000 1528
>13000 ::;;14000 14000 1561
>14000 ::;;15000 15000 1592
>15000 ::;;16000 16000 1623
>16000 ::;;17000 17000 1653
>17000 ::;;18000 18000 1684
>18000 ::;;19000 19000 1713 1713
>19000 ::;;20000 20000 1741 1741
>20000 ::;;20885 20885 1767 1767 Notes:
1.
- 1. Rod Rod worth worth data data assumes assumes the starting starting point is is rods atat thethe Rod Rod Insertion Limit.
Insertion Limit. 2.
- 2. The The rod rod worth worth data data represents represents negative However, STP-29.1, negative reactivity. However, STP-29.2 and STP-29.1, STP-29.2 STP-29.5 have and STP-29.5 been written have been to handle written to the the correct correct sign sign convention convention when when the the above data is above data entered as is entered Enter the number. Enter as aa positive number. the above above numbers directly into numbers directly the into the STP.
STP. 3.
- 3. ARI-1 ARI-1 isis defined defined as as All All Rods Rods In In -- less
-- the most less the reactive rod.
most reactive rod. 4.
- 4. For multiple stuck rods, For multiple stuck rods, the the ARl-l ARI-1 value value on on Page Page 1 1 of of this this curve should curve should be reduced by be reduced the following by the calculation:
following calculation: [KUR xx WSR [KUR 1.75] ++ [WSR WSR xx 1.75J [WSR xx 0.75] 0.75] where KUR = where KUR = Number Number of of known known untrippable untrippable rods (does not rods (does not include rod assumed include rod assunied stuck in ARl-l stuck in table) ART-i table) and and WSR WSR == Worst Worst stuck stuck rodrod (i.e. (i.e. most most reactive rod) reactive rod) Page 22 of2 Page of 2
Westinghous Westinghouse e Proprietary Class22 ProprietaryClass PCB-1-VOL 1-CRV78 PCB-I-VOLI-CRV78 UNlT 11CYCLE UNIT CYCLE 23 CURVE 78 23 CURVE 78 T~9tal P,-rn,. T,-1 Defect l,-
,pOJA7er fl4r-- SQM for fl1E CatfJl1atjops KY REV. '6 REV.
APPROVED:: ~<t" fWtJ j"y pry(j#, 4..-,,,,,.- zø
,1#
APPROVED ENGINEERING ENGINEERI SUPPORT MANAGER NG SUPPORT MANAGER DATE DATE Power Defect Power Defect (pcm) (pern) for for Shutdowit Shutdown Margin Margin Calculations Calculations Bumup Range Burnup Range Power Level Power Level (%) (%) (MWD/MTU)) (MWD/MTU 00 10 10 20 20 30 30 40 40 50 50 60 60 70 70 80 80 W 9U 100 100
~150 150 00 361 361 537 537 717 717 898 898 958 958 1019 1019 1119 1219 j 1119 1219 1326 1432 1326 1432
> 150
> 150 ~1000 1000 00 351 351 522 522 701 701 879 879 943 943 1006 1006 1106 1206 1106 1206 1307 1307 1409 1409
> 1000 ~2000
> 1000 2000 00 330 330 495 495 667 667 839 839 903 903 967 967 1068 1169 1068 1169 1265 1265 I 13611361
>2000
> 2000 ~3000 3000 00 317 317 476 476 647 818 818 879 879 941 1041 1041 1142 1142 1237 1237 1332 1332
>3000
> 3000 ~4000 4000 0 326 326 489 664 839 901 901 964 1062 1062 1161 1161 1261 1261 1360 1360
> 4000 ~ 5000
>4000 0 344 344 514 697 879 879 942 942 1004 1004 1103 1103 1202 1202 1306 1306 1410 1410
> 5000 ~6000
> 5000 6000 0 362 539 729 919 982 1045 1045 1144 1242 1459 1351 I 1459 I
> 6000 6000 ~7000 7000 0 388 388 576 774 972 1037 1103 1202 1301 1202 1301 , 1416 1416 I! 1531 1531
> 7000 ~8000
> 7000 8000 0 414 414 613 818 1024 1092 1160 1260 1360 1481 1603 1603
> 'woo
>8000<9000< QOOO 0 440 651 863 *0 1074 ,Jl7!~ 1147 , 1220 1lement #12 I JElement 1558 1684 I >
> 9000 9000 ~10000 10000 0 466 690 907 1124 1202 1280 1391 1503 1634 1765 176511
>10000
>10000 ~11000 11000 0 492 728 950 1173 1258 1344 1461 1579 1717 1854 1854
>11000
>11000 ~12000 12000 0 518 766 994 1222 1315 1408 1531 1655 1800 1944
>12000
>12000 ~13000 13000 0 543 804 1035 1267 1369 1471 1603 1734 1884 2034
>13000
>13000 ~14000 14000 0 567 841 1077 1077 1313 1313 1424 1424 1535 1535 1674 1813 1674 1813 1968 1968 2123
>14000
>14000 ~15000 15000 0 589 875 1115 1356 1477 1597 1744 1890 2054 2217
>15000
>15000 ~16000 16000 00 611 908 1153 1153 1399 1399 1529 1529 1660 1660 1813 1813 1967 1967 2139 2310
>16000
>16000 ~17000 17000 0 633 940 1189 1189 1438 1438 1578 1578 1718 1718 1882 1882 2046 2223 2400 2400
>17000
>17000 ~18000 18000 00 654 654 971 971 1225 1225 1478 1478 1627 1627 1777 1777 1951 1951 2125 2125 2307 2307 2489 2489
>18000
>18000 ~19000 19000 00 673 673 1001 1001 1259 1259 1516 1516 1677 1677 1837 1837 2020 2203 2203 2392 2392 2582 2582
>19000
>19000 ~20000 20000 00 692 692 1031 1031 1293 1293 1554 1554 1726 1726 1897 1897 2089 2089 2280 2280 2477 2477 2674 2674
>20000
>20000 ~20885 20885 00 709 709 1057 1057 1323 1323 1590 1590 1771 1771 1953 1953 2152 2152 2351 2351 2554 2554 2757 2757 Notes:
Notes: 1.1. STP-29.1, STP-29.1, STP-29.2 STP-29.2 and and STP-29.5 STP-29.5 have have been been written written to handle the to handle correct sign the correct sign convention convention when the above when the data isis above data entered entered as as aa positive positive number. number. Enter Enter the the above above numbers directly into numbers directly the into the STP. STP.
COLR for FNP Unit 1 1 Cycle 23 Revision 00 Page 10 10 of 13 13 Figure 1 1 Rod Bank Insertion Limits versus Rated ThwrmI Thermal Power KEY Elements 4 & 5 C
.' .. "";,, i' ."'" ','i'd.",,".' ,'" i',..' "'!'TY"!'(T ","i"i" '~'.
1...- (.552,225) II" , 200 II" 1"'- ,(1,187) -_
~
175 1.1
- ':' :,;~
II"
- ':" I:':-J"~\ :"";' , 'OC' ..
- '" :.,' :"", :" :,. .1:
II" Banke 1.1
'2 C
~
==
150 .,. !.I I I I I I I I I I I
!.I :
"C
.r: y =( 1.00-0,070 187 - 0,000 )0,900 _ 0,070)+ 0,000 l.I'
;: 1.1' y = 166.9 (rounded using 4signficant digits) !.I :
~ 125
- o. II" => 167sleps 2
!2 U) if not calculated and only read from graph ...- ,S s::
C (0,114) r- then> 165 And < 170; Therefore Half the accuracy of the scale !.I , 00 => 167,5 J Ef/)
- 100 00 c..
0 !.I BankO 1 1 s:: C cu llJ "C 75 ...- " 00 !.I 0::: 50 !.I 1.1 ; 25 II"
.,. /
(.070,0) ~ i o0 I I I I 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of RATED THERMAL POWER Fully Withdrawn shall be the condition where control rods are at a position within the interval ~ 225 and ~ 231 steps withdrawn. Note: The Rod Bank Insertion Limits are based on the control bank withdrawal sequence A, B, C, D and a control bank tip-to-tip distance of 128 steps.
FNP HLT-33 ADMIN FNPHLT-33ADMIN A.21.A A.2.1.A HANDOUT Pg 11 of I1 CONDITIONS When II tell you to begin, you you are to Determine Determine if Shutdown Shutdown Margin using STP-29.5, Margin is adequate using STP-29.5, SHUTDOWN MARGIN CALCULATION IN MODES 11 AND 22 (TAVG 2: 547°F), for Unit 1. 1. The conditions under which this task is to be performed are:
- a. Unit 11 is stable at 90% with the ramp on hold
- b. Bank D D indicates 192 by Group Demand.
- c. Seven of the Bank D rods (H2, B8, H14, KIO, K6) are at 192 steps by DRPI.
HI4, F6, FlO, Kb,
- d. Rod P8, in the D bank, has been determined to be Stuck.
- e. 162 steps by DRPI.
Rod P8 is at 162
- f. All other rods are at 229 steps.
- g. MWD/MTU burnup.
Core burnup is 9,800 MWDIMTU
- h. FNP-I-STP-29.5, SHUTDOWN MARGTN FNP-1-STP-29.5, MARGIN CALCULATION IN MODES 1I AND 22 (TAVG 2:
547°F), initial conditions are satisfied.
- i. FNP-I-STP-29.5 starting at step 5.1 and identify The Shift Supervisor has directed you to complete FNP-1-STP-29.5 whether or not emergency boration is required.
06118/01 10:31:04 06/18/01 10:31 :04 FNP-1-STP-29.5 FNP-I-STP-29.5 April 21, 2000 Revision 4 FARLEY NUCLEAR PLANT SURVEILLANCE TEST PROCEDURE FNP- 1 -STP-29.5 FNP-I-STP-29.5 SS A FF E T Y SHUTDOWN MARGIN CALCULATION IN MODES 11 AND 2 (TAVG 2 547°F) R E L A T E D PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use ALL Reference Use Information Use Approved: C. D. COLLINS Operations Manager Date Issued _4-'4-27-00
--=-27=---"-00"--_ _ _ _ __
06I18/0 10:31:04 06118/01 FNP-1-STP-29.5 F ARLEY NUCLEAR PLANT FARLEY SURVEILLANCE TEST REVIEW SHEET SURVEILLANCE TEST NO. TECHNICAL SPECIFICATION REFERENCE FNP-I-STP-29.5 FNP-1-STP-29.5 TR 13.1.1; LCO 3.1.4; LCO 3.1.5; LCO 3.1.6 TITLE MODE(S) REQUIRING TEST: SHUTDOWN MARGIN CALCULATION IN MODES 11 AND 2 11 *,2* (TAVG ;;:: 547°F) *See special test exceptions of above specifications TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER) PERFORMED BY DATE/TIME__________________ DATE/TIME COMPONENT OR TRAIN TESTED (if applicable) ((1] ENTIRE STP PERFORMED ((j] FOR SURVEILLANCE CREDIT [] {] PARTIAL STP PERFORMED: [] [J NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL: TEST COMPLETED: ((j] Satisfactory ((]Unsatisfactory
] Unsatisfactory
((]The
] The following deficiencies occurred:
(()) Corrective action taken or initiated: SHIFT FOREMAN REVIEW REVIEWED BY BY___________________________________ DATE. DATE
] Procedure properly completed and satisfactory
((]Procedure ((]Comments:
] Comments:
TECHNICAL GROUP- GROUP REACTOR ENG REVIEW REVIEWED BY DATE_______________ DATE ((1] Satisfactory and Approved ((1] Comments: Revision 4
06/18/01 10:31:04 06/18/01 10:31:04 FNP-1-STP-29.5 FNP-1-STP-29.5 TABLE OF TABLE OF CONTENTS CONTENTS Procedure Contains Contains Number of of Pages Body ......................................................... 2 Shutdown Margin ..................................... 33 STRS ........................................................ 11 Page 11 of 11 Revision 4
06118/01 10:31:04 06/18/01 10:31:04 FNP-1-STP-29.5 FNP-I-STP-29.5 FARLEY NUCLEAR PLANT FARLEY NUCLEAR PLANT UNIT 11 UNIT SURVEILLANCE TEST PROCEDURE STP-29 STP-29.5.5 SHUTDOWN MARGIN CALCULATION IN MODES 11 AND 22 (TAVG SHUTDOWN ~ 547°F) 547°F) 1.0 1.0 Purpose 1.1 1.1 The purpose of this procedure is to verify that the SHUTDOWN MARGIN is greater than the limits of the Technical Requirements Manual TR 13.1.1 13 .1.1 as Specifications in Modes 11 or 2: directed by Technical Specifications 1.1.1 One or more rod(s) untrippable (LCO 3.1.4), 1.1.2 rode s) not aligned within 12 steps of their group step counter One or more rod(s) demand position (LCO 3.1.4), 1.1.3 One or more shutdown banks not within insertion limits specified in the COLR (LCO 3.1.5), COLR(LCO 1.1.4 Control bank insertion, sequence, or overlap not within limits specified in the COLR (LCO 3.1.6). (This condition does not affect shutdown margin unless control banks are below insertion limits) 2.0 Acceptance Criteria 2.1 The Shutdown Margin shall be greater than or equal to the value specified in the COLR. 3.0 Initial Conditions HBF 3.1 The revision of this procedure has been verified to be the current revision and correct unit for the task. (OR 1-98-498) HBF 3.2 7°F. 4 TAVG5 HBF 3.3 1 °F of programmed value. (Needed for Power Defect to be accurate) TAVG +/- 1°F HBF 34 3.4 The plant is in Mode 11 or 2 with Keff ~ 1. HBF 3.5 Technical Specifications required action entered to verify SDM to be within the limits provided in the COLR OR QE Shift Supervisor desires to perform. Revision 4
06118/01 10:31:04 06/18/01 10:31:04 FNP-1-STP-29.5 4.0 4.0 Precautions and Precautions and Limitations Limitations 4.1 4.1 Read all Read all curves curves as as possible as accurately as possible OR most conservatively. OR most conservatively. 4.2 Observe proper algebraic sign notation throughout the calculation. 4.3 shutdown margin, THEN IF necessary to emergency borate due to inadequate shutdown consideration should be given to tripping the reactor and entering FNP-1-EEP-0, FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION concurrent with the emergency boration. boration. 5.0 Instructions NOTE: ** For calculating shutdown margin at power, the amount of reactivity by which the reactor would be subcritical from its present condition must be determined. If the reactor were to shutdown instantaneously, the changes in reactivity would be from control rod position and power defect. In the instant that the reactor shut down, reactivity changes from xenon, samarium and boron concentration would be zero. 5.1 Enter the information required on the attached calculation sheets and calculate the shutdown margin. NOTE:
- Verification of shutdown margin calculation by a licensed individual other than the test performer, should take place as soon as practical, and any differences resolved immediately immediately..
- A Shift Foreman that serves as verifier of the calculation may also serve as reviewer on the Surveillance Test Review Sheet.
5.2 Verify shutdown margin calculated in step 5.1. 6.0 References 6.1 Technical Specifications: LCOs 3.1.4, 3.1.5, & & 3.1.6. 6.2 Technical Requirement Manual TR 13.1.1 6.3 Core Operating Limits Report (COLR). Revision 4
06118/0110:31:04 06/18/01 10:31:04 FNP-1-STP-29.5 FNP-l-STP-29.5 SHUTDOWN MARGIN IN IN MODES 11 AND 22 A. PRESENT CONDITIONS A.l1 A. Core Burnup --- MWDIMTU MWD/MTU A.2 Power Level. % A.3 Determine number of penalty steps for ROD BANKS below RIL. RIL computer reading from % to steps) (Use COLR or convert the RJL A.3.a Record data in table ROD BANKRIL BANK RIL BANK STEPS BELOW BANKS HEIGHT DEMAND RIL CBA FULL OUT CBB FULL OUT CBC CBD SDA FULL OUT SDB FULL OUT TOTAL STEPS BELOW RIL a
' - _ _ _ _ _ _ _ _ .1 of 3 Page 11 of3 Revision 4
10:31:04 06/18/01 10:31 :04 FNP-1-STP-29.5 A.4 Determine number of penalty steps for RODS below RlL RIL which were not counted in A.3 (Rods below RIL on DRPI when the BANK demand is above RIL) (Use COLR or convert the RIL computer reading from % to steps) A.4.a Record data in table ROD NUMBER RIL POSITION DRPI POSITION DIFFERENCE TOTAL STEPS BELOW RIL I I I_. _------_
.... .1 B. SHUTDOWN MARGIN NOTE: Write the values from Curves 77 & & 78 directly into the surveillance test.
The correct sign convention has been entered in the STP. B.1 Rod worth for all control and shutdown banks at zero steps at r - - - - - - - - - - -, (A.1) Present Burnup (A. (A.2)..
- 1) and Power Level (A.2) ,, (-)
() pcm , (Curve 77 Page 1) i (Curve 77 Page 1) , 1... _ _ _ _ _ _ _ _ _ _ ... L. B.2 Penalty value of rod banks below insertion limit: _ _ _ steps x 75 pcm/step =
,()
L (+) L __________ ... pcm P , , (A.3.a) B.3 Penalty value of individual rods below RIL which were not counted in A.3 (Rods below RlL RIL on DRPI when the BANK demand is above RIL) r------------ _ _ _ steps xX 10 pcm/step = ,, (+) I (+) ____________ 1 pcm' pcm (A.4.a) of 3 Page 2 of3 Revision 4
06/18/01 10:31:04 06118/01 FNP-1-STP-29.5 B.4 Stuck 1 / Untrippable Rod penalty: (B.4.a is N/A and B.4.b is zero if there are no stuck/untrippable rods) B.4.a Worth of most reactive rod worth at present burnup (A.1) (-) () _ _ _ _pcm from Curve 77 pg. 2 Stuck!untrippable rods B.4.b Calculate worth of Stuckluntrippable [ x (-) () 1.75] + x 1.7S] + [(-) [() x 0.7S] 0.75] = (-)
= () _ _ _ pcm Stuck/
(# Stucki (B.4.a) (B.4.a) untrippable rods) (Most reactive (Most reactive rod worth) rod worth) B.5 B.S Penalized rod worth considering stuckluntrippable rods, misaligned rods, rods below the insertion limit, and uncertainty: (
-----------., (
[(-) _ _ _++ _ _ ++ [(-.1-) - (-) 1x 0.9 (I (()) L pcm ( L __________ _
- (-)_____
(B.1) (B.2) (B.3) (B.4.b) B.6 Power Defect at Power Level (A.2) and Burnup (A. (A.1) 1) (Curve 78). (-) () _ _ _ _pcm B.7 Void Collapse Defect. 50 pcm (+) _--'S"-"O'---_pcm B.8 Available Shutdown Reactivity: I - ( - - - - - ---- - , ()--- 1_ _ _ _ _ ()_______ ()__________
+
+ so 50
( L ______ __ ~c~ pcmj~ ( (B.5) (B.6) (B.7) B.9 Shutdown Margin in excess of required Shutdown Margin (B.8 - Required SDM from the COLR): r - - - - - - - - - - -(I O____ pcm (-) ()__________ () 1770 pcm : () pcm : (B.8) Required SDM i L... (SDMExcess) (SDMEXCeSS) ( L fromtheCOLR from the COLR B.10 If B.9 is positive, THEN emergency borate per FNP-1-AOP-27.0, EMERGENCY IfB.9 BORATION, to establish the required shutdown margin otherwise Shutdown Margin is adequate for the Present plant condition. Date: Date:____________________ Performed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: Date:___________________ Verified by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ of 3 Page 33 of3 Revision 4
Westinghous Westinghouse e Proprietary Class22 ProprietaryClass PCB-1-VOL 1-CRV77 PCB-l-VOL1-CRV77 UNIT 11CYCLE UNIT CYCLE 23 CURVE 77 23 CURVE 77 ControlRod Control Rod Worth Worth for SDM Calculations for SDM Calculations REV.~ REV.___ APPROVED:: tj(~ J:. f(<<.; Iv,- r kya.i PI-Yo", ?'?r,n"/V 7J# APPROVED ENGINEERING ENGINEERI SUPPORT MANAGER NG SUPPORT MANAGER DATE DATE ARI-l Rod ART-i Rod Worth Worth (pcm) (pcm) for for Shutdown Shutdown Margin Margin Calculations Calculations BumupRange Burnup Range Power Level Power Level (%) (%) (MWDIMTU) (MWDIMTU ) 00 10 10 20 20 30 30 40 40 50 50 60 60 70 70 80 80 90 90 100 100
~150 150 4587 4587 4710 4710 4831 4831 5071 5071 5311 5311 5483 5483 5655 5655 5792 5792 5927 5927 6162 6162 6397 6397
>150
> 150 ~1000 1000 4667 4667 4801 4801 4935 4935 5180 5180 5425 5425 5594 5594 5762 5762 5905 5905 6048 6048 6285 6285 6523 6523
> 1000
>1000 ~2000 2000 4717 4717 4867 4867 5017 5017 5267 5267 5517 5517 5680 5680 5844 5844 5995 5995 6145 6145 6384 6384 6623 6623
> 2000
> 2000 ~3000 3000 4755 4755 4909 4909 5063 5063 5320 5320 5578 5578 5740 5740 5902 5902 6052 6052 6201 6201 6442 6442 6683 6683
> 3000
>3000 ~4000 4000 4818 4818 4975 4975 5131 5131 5396 5396 5660 5814 5814 5969 5969 6113 6113 6257 6257 6483 6483 6708 6708
>4000
> 4000 ~5000 5000 4767 4920 4920 5072 5346 5346 5619 5619 5778 5778 5938 5938 6073 6073 6208 6208 6439 6439 6670 6670
> 5000
>5000 ~6000 6000 4717 4865 5013 5013 5296 5296 5579 5743 5743 5906 5906 6033 6033 6159 6395 6395 6631 6631
> 6000
>6000 S~7000 7000 4689 4827 4965 5254 5542 5542 5714 5885 5885 6001 6001 6118 6355 6593 6593
> 7000
> 7000 ~8000 8000 4660 4788 4916 5211 5506 5685 5864 5970 6076 6316 6555 6555
> 8000
>8000 ~9000 59000 4646 4765 4884 5182 5480 5669 5857 5955 6052 6292 6531 6531
> 9000 9000 ~10000 510000 4632 4742 4852 5154 5455 5652 5850 5939 6028 6268 6507 6507
>10000
>10000 ~11000 511000 4622 4725 4828 5129 5431 5641 5850 5933 6016 6253 6490 6490
>11000
>11000 ~12000 512000 4612 4707 4803 5105 5408 5629 5850 5927 6004 6239 6473
>12000
>12000 ~13000 513000 4617 4706 4795 5096 5398 5631 5865 5937 6010 6242 6475 6475
>13000
>13000 ~14000 514000 4621 4704 4787 5087 5387 5633 5879 5947 6015 6245 6476
>14000
>14000 ~15000 515000 4631 4709 4787 5086 5385 5642 5900 5964 6028 6256 6256 6485 6485
>15000
>15000 ~16000 516000 4641 4714 4787 5085 5382 5652 5921 5981 6041 6267 6493 6493
>16000
>16000 ~17000 17000 4662 4731 4800 5096 5096 5391 5669 5947 6004 6062 6286 6510
>17000
>17000 ~18000 518000 4682 4748 4813 5107 5400 5687 5973 6028 6083 6304 6526 6526
>18000
>18000 ~19000 519000 4709 4709 4771 4771 4833 4833 5125 5125 5418 5418 5710 5710 6002 6002 6056 6056 6109 6109 6328 6328 6547 6547
>19000
>19000 ~20000 20000 4735 4794 4852 5144 5144 5435 5435 5734 5734 6032 6032 6083 6083 6135 6135 6351 6351 6568 6568
>20000
>20000 ~20885 20885 4760 4760 4818 4818 4876 4876 5165 5165 5454 5454 5759 5759 6063 6063 6112 6112 6161 6161 6377 6377 6592 6592 Notes:
Notes:
- 1. Rod
- 1. Rod worth worth data data assumes assumes the the starting starting point point isis rods rods atat the Rod Insertion the Rod Insertion Limit. bank isis below If aa bank Limit. If the RIL, below the RIL, reduce the reduce the table table value value byby 75 75 pcm pcm for for each each step step below below the RIL.
the RIL. 2.2. The rod worth data represents The rod worth data represents negative negative reactivity. reactivity. However, STP-29.2 and STP-29.1, STP-29.2 However, STP-29.1, and STP-29.5 written to been written have been STP-29.5 have to handle the correct handle the correct sign sign convention convention when when the the above above data data is is entered entered as as a a positive positive number. number. Enter Enter the the above above numbers numbers directly directly into into the the STP. STP. 3.3. ARI-l ARI-1 isis defined defined as as All All Rods Rods InIn -- less
-- less the the most most reactive reactive rod. The SDM rod. The that one requires that calculation requires SDM calculation rod be one rod assumed be assumed stuck.
stuck. Therefore, Therefore, useuse thethe data data directly directly from from the above when table above the table when there are not any known there are not any known stuck rods. stuck rods. of 2 Page 11 of2 Page
Westinghouse Proprietary Westinghouse Class 22 ProprietaryClass PCB-1-VOL1-CRV77 PCB-I-VOLl-CRV77 UNIT 1I CYCLE UNIT CYCLE 23 CURVE 77 23 CURVE 77 Control Rod Control Rod Worth Worth for SDM Calculations for SDM Calculations REV.~ REV. APPROVED: y~ f.ty Ie'r $trlIi'l fU:'Hr
~ 1.(-/5 ~O, APPROVED: A:
fi ENGINEERING SUPPORT ENGINEERING SUPPORT MANAGER MANAGER DATE DATE Worth of Worth of Most Most Reactive Reactive Rod Rod (pcm) (pcm) for for Shutdown Margin Calculations Shutdown Margin Calculations Burnup Range Burnup Range Power Power Level Level (MWD/MTU) (MWD/MTU) 0% to 0% to 100% 100%
~150 150 658 658
> 150 150 ~1000 1000 676 676
> 1000
>1000 ~2000 2000 732 732
> 2000 3000
~3000 781 781
> 3000 ~4000 4000 889
>4000 ~5000 5000 1024 1024
> 5000 ~6000 6000 1160
> 6000 ~7000 7000 1232
> 7000 ~8000 8000 1304
> 8000 ~9000 9000 1355
> 9000 ~10000 10000 1406
>10000 ~11000 11000 1450
>11000 ~12000 12000 1494
>12000 ~13000 13000 1528
>13000 ~14000 14000 1561
>14000 ~15000 15000 1592 1592
>15000 ~16000 16000 1623 1623
>16000 ~17000 17000 1653 1653
>17000 ~18000 18000 1684 1684
>18000
>18000 ~19000 19000 1713 1713
>19000
>19000 ~20000 20000 1741 1741
>20000
>20000 ~20885 20885 1767 1767 Notes:
Notes:
- 1. Rod
- 1. Rod worth worth data data assumes assumes the the starting starting point point is is rods rods at at the the Rod Rod Insertion Limit.
Insertion Limit. 2.
- 2. TheThe rod rod worth worth data data represents represents negative negative reactivity. However, STP-29.1, reactivity. However, and STP-29.5 STP29.2 and STP-29.1, STP-29.2 have been STP-29.5 have been written to handle written to handle the the correct correct sign sign convention convention when when the the above above data entered as data isis entered as aa positive the above Enter the number. Enter positive number. above numbers directly into numbers directly the into the STP.
STP. 3.
- 3. ARI-1 AR1-1 isis defined defined as as All All Rods Rods In In --less
-- less the the most most reactive reactive rod.rod.
4.4. For For multiple multiple stuck stuck rods, rods, the the ARI-l ARI-1 value value onon Page Page 11 of of this this curve be reduced should be curve should by the reduced by the following calculation: following calculation: [KUR [KUR xx WSR 1.75] ++ [WSR WSR xx 1.751 {WSR xx 0.75] 0.75] where where KUR KUR == Number Number of known untrippable of known untrippable rods (does not rods (does include rod not include assumed stuck rod assumed ART-i table) in ARI-l stuck in table) and and WSR WSR == Worst Worst stuck stuck rodrod (i.e. (i.e. most most reactive reactive rod) rod) Page 22of2 Page of 2
Westinghous Westinghouse e Proprietary Class 22 Proprietary Class PCB-1-VOL I-CRV78 PCB-I-VOLI-CRV78 UNIT 11 CYCLE UNIT CYCLE 23 CURVE 78 23 CURVE 78 Total Total Power Power Defect Defect for for SDM SDM Calculations Calculations REV.~ REV. APPROVED:: APPROVED ~.t'" (u,,' !,.,.. (fry(}#. Crr'<1t'r "/# ENGINEERING ENGINEERI SUPPORT MANAGER NG SUPPORT MANAGER DATE Power Defect Power Defect (pcm) for Shutdown (pem) for Shutdown Margin Margin Calculations Calculations Bumup Range Burnup Range Power Level Power Level (%)(%) (MWD/MTU)) (MWD/MTU 00 10 10 20 20 30 30 40 40 50 50 60 60 70 70 80 80 90 90 100 100
- 150 150 00 361 361 537 537 717 717 898 898 958 958 1019 1019 1119 1119 1219 1219 1326 1326 1432 1432
> 150
> 150 ::; 1000 1000 00 351 351 522 522 701 701 879 879 943 943 1006 1006 1106 1106 1206 1206 1307 1307 1409 1409
>1000
> 1000 ::;2000 2000 00 330 330 495 495 667 839 839 903 903 967 967 1068 1068 1169 1169 1265 1265 1361 1361
>2000
> 2000 ::;3000 3000 00 317 317 476 647 818 879 941 1041 1041 1142 1142 1237 1237 1332 1332
>3000
> 3000 ::;4000 4000 0 326 326 489 664 839 901 964 1062 1062 1161 1161 1261 1261 1360 1360
>4000
> 4000 ::; 5000 00 344 514 697 879 942 1004 1103 1202 1306 1410
> 5000
> ::; 6000 0 362 539 729 919 982 1045 1144 1242 1351 1459
> 6000
> ::;7000 7000 0 388 576 774 972 1037 1103 1202 1301 1416 1531 1531
> 7000 ::; 8000 0 414 613 818 1024 1092 1160 1260 1360 1481 1.603 1603
> 8000
>8000 ::;
90009000 0 440 651 863 1074 1147 1220 1326 1431 1558 1684
> 9000 >9000 510000 10000 0 466 690 907 1124 1202 1280 1391 1503 1634 1765 >10000 ::;11000 11000 0 492 728 950 1173 1258 1344 1461 1579 1717 1854 >11000 ::;12000 12000 0 518 766 994 1222 1315 1408 1531 1655 1800 1944 >12000 ::;13000 13000 0 543 804 1035 1267 1369 1471 1603 1734 1884 2034 >13000 ::;14000 14000 0 567 841 1077 1313 1424 1535 1674 1813 1968 2123 >14000 ::;15000 15000 0 589 875 1115 1356 1477 1597 1744 1890 2054 2217 2217 >15000 ::;16000 16000 0 611 908 1153 1153 1399 1399 1529 1529 1660 1660 1813 1813 1967 1967 2139 2310 >16000 ::;17000 17000 0 633 940 1189 1438 1578 1718 1882 1882 2046 2223 2400 >17000 ::;18000 18000 0 654 971 1225 1225 1478 1478 1627 1627 1777 1777 1951 1951 2125 2307 2489 >18000 ::;19000 19000 0 673 1001 1001 1259 1259 1516 1516 1677 1677 1837 1837 2020 2203 2203 2392 2392 2582 >19000 >19000 ::;20000 20000 00 692 1031 1031 1293 1293 1554 1554 1726 1726 1897 1897 2089 2280 2477 2674 2674 >20000 >20000 ::;20885 20885 00 709 1057 1057 1323 1323 1590 1590 1771 1771 1953 1953 2152 2351 2554 2757 Notes:
Notes:
- 1. STP-29.1,
- 1. STP-29.1, STP-29.2 STP-29.2 and and STP-29.5 STP-29.5 have written to been written have been handle the to handle correct sign the correct when the convention when sign convention the above data isis above data entered entered asas aa positive positive number.
number. Enter Enter the the above above numbers numbers directlydirectly into into thethe STP. STP.
COLR for CQLR for FNP FNP Unit Unit 11 Cycle Cycle 23 23 Revision 00 Revision Page 10 Page of 13 10 of 13 Figure Figure 11 Insertion Limits Bank Insertion Rod Bank Rod versus Rated Limits versus Rated Thermal Power Power Fully Withdrawn - 225 Fully 231 steps, inclusive 225 to 231 inclusive 225 225
- : : : : :i:I: : : : : : : : : : : : : : : : : :; : : : : : : : : : ::
HE 1 1 1 I I I L -
- (.552,
(.552,225)225)
~
200 200 (1,187)_ (1,187) _
~
175 175 0 i.I' BankC I.... Banke V'
'2 1/
- = 150 150 II i.I' 101'
~
j-
"C
.l:
~ 125
.125
.s II i.I' II 1/
~
(I, c: (0,114) - II 0
'iii 100 - - - -
0 t.... a.
- 0. i.I' BankD Bank D c:
ra co "C 75 0 1/ 0:: 50 1/ V' 25
, L
~
~ (.070,0) o I I I I I
°l?l 0.0 0.1 0.2 0,3 0.3 0.4 05 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of RATED THERMAL POWER Fully Withdrawn shall be the condition where control rods are at a position within the interval ~ 225 and S 231 steps withdrawn.
Note: The Rod Insertion Limits are based on the control bank withdrawal Rod Bank Insertion sequence A, B, C, D and a control bank tip-to-tip distance of 128 128 steps.
FNP HLT-33 ADMIN Page 11 of 55 A.3.1.R Radiation Control ADMIN G2.3.9 - RO CRO-A.3. CRO-A.3.1.R1 .R TITLE: Calculate the Maximum Permissible Stay Time within Emergency Dose Limits. PROGRAM APPLICABLE: SOT SOCT____ SOCT OLT ---.2L X LOCT____ LOCT_ _ ACCEPTABLE EVALUATION METHOD: --.L X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM ~ X CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: SIMULATORIC N/A NIA ALTERNATE PATH TIME CRITICAL PRA____ PRA"_ _ lPM DIRECTIONS: JPM
- 1. Initiation of task may be in group setting, evaluation performed individually upon completion.
- 2. The references for this task will be provided as listed or the student may be provided a computer with a generic exam login and access to the EXAM reference disk.
- 3. Elements 11 through 7 may be evaluated by reviewing the responses on the Handout.
TASK STANDARD: Required for successful completion of this lPM: JPM:
- Calculate dose expected for Tasks 11 through 33
- Determine if a Repair team would exceed equipment protection emergency dose limits ofEIP- of EIP 14.0, Personnel Movement, Relocation, Re-Entry and Site Evacuation.
- Calculate the maximum allowable stay time for a task; or determine what tasks can be performed, if any, without exceeding limits.
Examinee: Overall JPM Performance: Satisfactory 0L1 Unsatisfactory U nsatisfactorv 0D Evaluator Comments (attach additional sheets if necessary) EXAMINER: EXAMINER: _ _ _ _ _ _ _ _ __ Developer Howard Fitzwater 1 1/06/09 11106/09 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLT-33 ADMIN A.3.1.R Page 2 of5 of 5 CONDITIONS When I tell you to begin, you are to Calculate the Maximum Permissible Stay Time within Emergency Dose Limits. The conditions under which this task is to be performed are:
- a. A General Emergency has been declared on Unit 1.
- b. lA1A RHR pump is air bound and must be vented per AOP-12, Attachment 1, RHR Pump Venting.
- c. The TSC has requested that 1lB B RHR pump motor bearing oil levels be checked and filled as required after restoring lA1A RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 1 1 to 20 minutes.
- d. You have been selected to perform the task.
- e. The tasks are provided in the table below, and estimated times and doses have been provided.
- f. Each task must be completed in the order listed.
- g. The Emergency Director (ED) directs you to perform the following with the information provided:
o0 Calculate the expected dose for tasks 11 through 33 and document in the table. o0 Determine the tasks, if any, for which you could be permitted to perform without exceeding the equipment protection emergency dose limits of 10 REM.
- If you will NOT exceed emergency dose limits prior to performing task 4, THEN calculate the maximum allowable stay time to complete task 4, and remain within the dose limits.
- IF you WILL exceed emergency dose limits prior to performing task 4, THEN identify the last tasks (if any) that you can complete without exceeding dose limits.
allowed! Time allowed/ Dose Task Location/Task description req'd reqd Rate Dose
# (minutes) (R!hr) 83' 83 lA 1A RHR Pump and HX rooms! rooms/ Vent rig installation and 1
1 30 5 31 venting too piping penetration room! Vent rig installation and 2 15 75 venting 121 piping penetration room! Vent rig installation and 3 venting Inspect lB RHR pump motor bearing oil levels and fill as 4 required Can you perform all of the tasks? (Circle one) YES / NO IF yes, then state the maximum permitted stay time for task #4. IF no, then state the highest sequential task # that can be performed, if any. INITIATING CUE: "You You may begin. begin."
FNP HLT-33 ADMIN A.3.1.R Page 33 of of55 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME
- 1. Determine the dose received for tasks 11 through 3. 1) Calculates (in REM)
- a. Task#1 Task #1 a. 2.66 {Range 2.6 to 2.7) 2.7} SS I U lhr (30min)x 5.3 1R/hr x( Ihr. )=2.66REM (30min)x5.31Rlhrx( = 2.66REM 60 mm) 60mm
- b. Task #2
- b. 4.938 {4.9 to 5.0} S /I U S
lhr (l5min)x 19.75R/hrx (15min)xI9.75Rlhrx( = 4.938REM Ihr. )=4.938REM k60mmn) 60mm
- c. Task #3 lhr c. 1.88 {1.8 {1.8to to 1.9} S/U S I U 5.65R / hr x( Ihr. ) =
(20min)x 5.65RI .88REM
=11.88REM 60min) 60mm NOTE: ** A Cue may be required to obtain responses for each element if the candidate does not clearly document results. Provide the Cue as stated on the Handout.
c1earl
- 2. Evaluates exposure within 10 REM for 2) Circles YES on handout -OR- OR S I U S/U completion of tasks 11 through 3. states that all tasks can be completed.
- a. Summation of Task 11 through 33 (2.66 +
OREM -(2.66 11OREM + 4.94 + )REM ~ 0 1 .88)REM
+ 1.88 a. 10 R is limit 0.52REM~0 0.52REM0
- b. Determines all tasks can be completed.
- b. 0.52 R remains available
- c. Circles the YES choice
- 3. Calculates stay time for task #4. 3) Documents or States: STAY S I U S
1 hr V60min = 4.493 min . time is 4.5 mins (0.52Rem, hr )(60min) (0.52Rem{ I 1=4.493mm
\7REM,A 7 REM hr )
1 .
. {Range: 3 min mm to 6 min}
RANGE :3mmnto6min {RANGE: 3 min_to _ 6min} STOP TIME Terminate when all elements of the task have been completed. CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) (*) before the element number.
FNP HLT-33HL T -33 ADMIN A.3.1.R A.3.1.R of55 Page 44 of GENERAL
REFERENCES:
- 1. FNP-0-EIP-14.0, ver 22 1.
- 2. FNP-0-M-1.0,ver
- 2. FNP-O-M-l.O, ver 18.0 18.0 KA: G2.3.4
- 3. KA:G2.3.4 RO 3.2 SRO 3.7 GENERAL TOOLS AND EQUIPMENT:
Provide/Acquire:
- 1. Computer with access to Exam Reference Disk, or EIP 14.0, ver 22.0 and M-1 .0, version 18.0.
M-1.0,
- 2. Calculator
- 3. pens/pencils 3.
- 4. Scrap paper Critical ELEMENT justification:
STEP Evaluation l.a CRITICAL - Task Objective 1l.b
.b CRITICAL - Task Objective l.c 1 .c CRITICAL - Task Objective 2 CRITICAL - Task Objective 33 CRITICAL - Task Objective COMMENTS:
FNP HLT-33 ADMIN A.3.1.R A.3.l.R HANDOUT Page 11 of 11 CONDITIONS When I tell you to begin, you are to Calculate the Maximum Permissible Stay Time within Emergency Dose Limits. The conditions under which this task is to be performed are:
- a. A General Emergency has been declared on Unit 1.
- b. 1AIA RHR pump is air bound and must be vented per AOP-12, AOP-I2, Attachment 1, RHR Pump Venting.
- c. The TSC has requested that lB IB RHR pump motor bearing oil levels be checked and filled as required after restoring 1AIA RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 11 to 20 minutes.
- d. You have been selected to perform the task.
- e. The tasks are provided in the table below, and estimated times and doses have been provided.
- f. Each task must be completed in the order listed.
- g. The Emergency Director (ED) directs you to perform the following with the information provided:
o Calculate the expected dose for tasks 11 through 33 and document in the table. o Determine the tasks, if any, for which you could be permitted to perform without exceeding the equipment protection emergency dose limits of 10 REM.
- If you will NOT exceed emergency dose limits prior to performing task 4, THEN calculate the maximum allowable stay time to complete task 4, and remain within the dose limits.
- IF you WILL exceed emergency dose limits prior to performing task 4, THEN identify the last tasks (if any) that you can complete without exceeding dose limits.
allowed! Time allowed/ Dose Task reqd Location/Task description req'd Rate Dose ff (minutes) (R!hr) 1A RHR Pump and HX rooms/ 83 IA 83' rooms! Vent rig installation and 1 30 5 31 venting too piping penetration room! Vent rig installation and 2 15 19 75 venting room! Vent rig installation and 121 piping penetration room/ 121' 3 20 5 65 venting Inspect IBlB RHR pump motor bearing oil levels and fill as 4 required re Can you perform all of the tasks? (Circle one) YES /! NO IF yes, then state the maximum permitted stay time for task #4. IF no, then state the highest sequential task # that can be performed, if any.
FNP HLT-33 ADMIN Page 11 of 55 Control ADMIN G2.3.9 - SRO A.3.1.S Radiation Control CRO-A.3. CRO-A.3.1.S1 .S TITLE: Calculate the Maximum Permissible Stay Time within Emergency Dose Limits. PROGRAM APPLICABLE: SOT SOCT SOCT____ OLT ~ X LOCT____ LOCT_ _ ACCEPTABLE EVALUATION METHOD: ~PERFORM X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: MIN 20 MTN SIMULATOR IC NUMBER: N/A NIA ALTERNATE PATH TIME CRITICAL PRA_ _ PRA____ JPM DIRECTIONS:
- 1. Initiation of task may be in group setting, evaluation performed individually upon completion.
- 2. The references for this task will be provided as listed or the student may be provided a computer with a generic exam login and access to the EXAM reference disk.
- 3. Elements 11 through 7 may be evaluated by reviewing the responses on the Handout.
TASK STANDARD: Required for successful completion of this JPM:
- Calculate dose expected for Tasks 11 through 33
- Determine if a Repair team would exceed equipment protection emergency dose limits ofEIP-of EIP 14.0, Personnel Movement, Relocation, Re-Entry and Site Evacuation.
- Calculate the maximum allowable stay time for a task; or determine what tasks can be performed, if any, without exceeding limits.
Examinee: Overall JPM Performance: Satisfactory D E1 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary) EXAMINER: EXAMINER: __________________ Developer Howard Fitzwater 11106/09 1 1/06/09 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLHLT-33 T -33 ADMIN A.3.1.S A.3.l.S Page 2 of 55 CONDITIONS When I tell you to begin, you are to determine if exposure is within emergency dose limits of EIP- EIP 14.0, Personnel Movement, Relocation, Re-Entry and Site Evacuation. The conditions under which this task is to be performed are:
- a. A General Emergency has been declared on Unit I. 1.
- b. IA RHR pump is air bound and must be vented per AOP-12, Attachment 1, RHR Pump 1A RHRpump Venting.
- c. The TSC has requested that 1lB B RHR pump motor bearing oil levels be checked and filled as 1A RHR and suggests using the same Repair team. The time required to required after restoring lA perform this task is unknown, but is estimated to range between 11 to 20 minutes.
- d. Ted and Joel have been selected to perform the task, their exposure information is stated below.
- e. The Tasks are provided in the table below, and estimated times and doses have been provided.
- f. Each task must be completed by both operators, and must be performed in the order listed.
- g. Both operators are expected to receive equal dose for each job.
- h. The Emergency Director (ED) directs you to perform the following with the information provided:
o Calculate the expected dose for tasks 11 through 33 and document in the table. o Determine the tasks, if any, for which the members of the team could be permitted to perform without exceeding the equipment protection emergency dose limits ofEIP-14.0. of EIP-14.0.
- If any member of the team will NOT exceed emergency dose limits prior to performing task 4, THEN calculate the maximum allowable stay time to complete task 4, and remain within the dose limits.
- IF any member of the team WILL exceed emergency dose limits prior to performing task 4, THEN identify the last tasks (if any) that the team can complete without either member exceeding dose limits.
allowed! Time allowed/ Dose Task I Location/Task description reqd req'd Rate Dose
# (minutes) (RJhr) 83' 83 lA1A RHR Pump and HX rooms/ Vent rig installation and 1 30 5 31 venting too piping penetration room/ Vent rig installation and 2 15 19 75 venting 121 piping penetration room/ Vent rig installation and 20 5 65 venting Inspect lB RHR pump motor bearing oil levels and fill as required Year-to-date DOSE Records (REM TEDE)
TED 1.26 JOEL 0.4 Can this team perform all of the tasks? (Circle one) YES / NO IF yes, then state the maximum permitted stay time for task #4. IF no, then state the highest sequential task # that can be performed, if any. INITIATING CUE: "You You may begin. begin."
FNP HLT-33 ADMIN A.3.1.S Page 33 of 55 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME
- 1. Determine the dose received for tasks 11 through 3. 1) Calculates (in REM)
- a. Task#1 Task #1 a. 2.66 {Range 2.6 to 2.7} SS/U
/ U lhr (30min)x 5.31RI hr x ( 1hr. )1=2.66REM (30min)x5.31R/hrxl = 2.66REM 60mmn) 60mm
- b. Task Task#2 #2
- b. 4.938 {4.9 to 5.0} S I/ U S
lui (15min)x19.75Rlhrx( (l5min)x19.75R/hrxl 1hr. )=4.938REM 60 60mm mm) 1 = 4.938REM
** Task #3
- c. Task#3 lhr c. 1.88 {1.8to
{1.8 to 1.9} S/U 5.65R /hr (20min)x 5.65RI hr xx( 1hr. ) = = 1.88REM
.88REM 60min}
60mm NOTE: ** A Cue may be required to obtain responses for each element if the candidate does not clearly document results. Provide the Cue as stated on the Handout. c1earl
- 2. Evaluates Team exposure within emergency 2) Circles YES on handout -OR- OR S I/ U S
limits of EIP-14.0 for completion of tasks 11 states that team can perform through 3. tasks 11 through 3.
- a. Emergency Dose limit for equipment a. 10 R is limit protection is 10 R and DOES NOT include current exposure.
- b. Summation of Task 11 through 33 OREM -(2.66 11OREM (2.66 +
+ 4.94 + )REM ~ 0 1 .88)REM
+ 1.88 b. 0.52 R remains available 0.52REM ~ 0
- c. Determines BOTH team members can c. Circles the YES choice complete all tasks.
- 3. Calculates stay time for task #4. 3) Documents or States: STAY S/U S / U 1 hr V60min time is 4.5 mins (O.52Rem, hr )(60min)
(0.52Rem{ I = 4.493 min
=4.493mm
\7REMA 7 REM hr )
( . .
-, mm) mm to 6 min)
{Range: 33 min RANGE :3mmnto6min {RANGE: 3 min_to _ 6min} STOP TIME Terminate when all elements of the task have been completed. CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) (*) before the element number.
FNP HLT-33 ADMIN A.3.1.S of 5 Page 4 of5 GENERAL
REFERENCES:
- 1. FNP-0-EIP-14.0, ver 22
- 2. FNP-O-M-1.0, FNP-0-M-1.0, ver 18.0 KA:G2.3.4
- 3. KA: G2.3.4 RO 3.2 SRO 3.7 GENERAL TOOLS AND EQUIPMENT:
Provide/Acquire: M- 1.0, version 18.0.
- 1. Computer with access to Exam Reference Disk, or EIP 14.0, ver 22.0 and M-1.0,
- 2. Calculator
- 3. pens/pencils
- 4. Scrap paper Critical ELEMENT justification:
STEP Evaluation l.a 1.a CRITICAL - Task Objective 1 .b 1.b CRITICAL - Task Objective 1 .c I.c CRITICAL - Task Objective 2 CRITICAL - Task Objective 33 CRITICAL - Task Objective COMMENTS: Teds year to date dose is used, the emergency dose limit will be exceeded and the expected response IF Ted's NO and highest task that can be completed is Task #3. for element 2 is "NO" Joels year to date dose is used and the Emergency dose is reduced by this value then the stay time IF Joel's will range from 0 mins to 1.1 mins. IF emergency dose limit of 25 Rem Then Stay time will be excessive. IF ADMIN dose limit of 2 REM used then NONE of the tasks can be performed, or Legal limit of 55 REM then Task #2 will be the highest.
FNP HLT-33 FNP HLT-33 ADMIN ADMIN A.3.l.S A.3.1.S HANDOUT HANDOUT Page 11 of Page of I1 CONDITIONS CONDITIONS When II tell When tell you you to to begin, begin, you you are are to to determine determine if exposure isis within if exposure dose limits within emergency dose limits of of EIP EIP-14.0, Personnel 14.0, Personnel Movement, Relocation, Re-Entry and Site Evacuation. Evacuation. The conditions conditions under which this task is to be performed are:
- a. A General Emergency has been declared on Unit 1. 1.
- b. 1A1A RHR pump is air bound and must be vented per AOP-12, Attachment 1, 1, RHR Pump Venting.
- c. The TSC has requested that lB 1B RHR pump motor bearing oil levels be checked and filled as required after restoring 1A1A RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 11 to 20 minutes.
perform the task, their exposure information is stated below.
- d. Ted and Joel have been selected to perform
- e. The Tasks are provided in the table below, and estimated times and doses have been provided.
- f. Each task must be completed by both operators, and must be performed in the order listed.
- g. Both operators are expected to receive equal dose for each job.
- h. The Emergency Director (ED) directs you to perform the following with the information provided:
o Calculate the expected dose for tasks 1 1 through 33 and document in the table. o Determine the tasks, if any, for which the members of the team could be permitted to perform without exceeding the equipment protection emergency dose limits of EIP-14.0. ofEIP-14.0.
** If any member of the team will NOT exceed emergency dose limits prior to performing task 4, THEN calculate the maximum allowable stay time to complete task 4, and remain within the dose limits.
- IF any member of the team WILL exceed emergency dose limits prior to performing task 4, THEN identify the last tasks (if any) that the team can complete without either member exceeding dose limits.
allowed! Time allowed/ Dose Task Location/Task description reqd req'd Rate Dose 44 (minutes) (RJhr) 83 1A RHR 83' R}{R Pump and HX rooms/ Vent rig installation and 1 30 5 31 venting 2 too piping penetration room/ Vent rig installation and 15 19 75 venting 121 piping penetration roorn/ Vent rig installation and 20 5 65 venting Inspect lB RHR pump motor bearing oil levels and fill as 7 required Year-to-date DOSE Records (REM TEDE) TED 1.26 JOEL 0.4 Can this team perform all of the tasks? (Circle one) YES / NO IF yes, then state the maximum permitted stay time for task #4. IF no, then state the highest sequential task # that can be performed, if any.
FNPHLT-33ADMIN FNP HLT-33 ADMIN Page 1 1 of ofl3 13 A.4.1.A A.4.l.A Emer Emergency & SRO ency Plan G2.4.14 - RO & CRO-362 TITLE: Make Initial Notifications As Required for an Emergency PROGRAM APPLICABLE: SOT SOCT OLT X LOCT X OLT~LOCT~ ACCEPTABLE EVALUATION METHOD: ~ X PERFORM ~ X SIMULATE EVALUATION LOCATION: 2L X Classroom PROJECTED TIME: 20 MIN TIME CRITICAL ~ X
*THIS JPM IS TIME CRITICAL*
JPM DIRECTIONS:
- 1. This task will be done in the simulator area where the Southern Link phones can be accessed.
- 2. The Candidate will have 15 minutes from the start time to complete the initial notifications, and then time to activate the ERO call-out system.
- 3. The evaluator, upon commencement of the JPM, shall fill in data on the Guideline 11 handout then provide both EIP-9.0 Guideline 11 and EIP-8.3 table 2 to the candidate.
TASK STANDARD: Required for successful completion of this JPM:
- Complete the ERO callout system per EIP-8.3 Table 2.
- Initiate notification using the Emergency Notification Network (ENN) to at least ONE state agency within 15 mins.
- Complete EIP-9.0 Guideline 1, form actions beginning at Step 00 through step X.
Examinee: Overall JPM 3PM Performance: Satisfactory 01 Unsatisfactory 0D Evaluator Comments (attach additional sheets if necessary) EXAMINER: _ _ _ _ _ _ _ _ __ Developer Howard Fitzwater 03/21/2010 03/2112010 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLT-33 FNP HLT-33 ADMIN ADMIN A.4.1.A AA.1.A Page Page 22 of of 13 13 CONDITIONS When II tell When tell you you to to begin, begin, you you are are to to make make initial initial notifications notifications as required for an as required an emergency emergency and and activate the emergency callout system. The conditions under which which this task performed are: task is to be performed are:
- a. AA General Emergency has just Shift Manager due to an event on Unit 1.
been declared by the Shift just been 1.
- b. The Shift Manager has handed you EIP-8.3, Table 2, and EIP-9.O, EIP-9.0, Guideline 1,1, GENERAL EMERGENCY RED INITIAL NOTIFICATION FORM.
- c. The Shift Manager has directed you to:
PERFORM the initial ENN notification over the Southern LINC ENN.
- PERFORIvI
- USE the SOUTHERN LINC and actually perform this function.
- The SOUTHERN LINC will be selected to WIDE AREA TRN ENN on the display.
- ACTIVATE the ERO callout system per EIP-8.3, Table 2.
- SIMULATE the phone call. DO NOT actually press any buttons on the telephone.
- If a FAX is required, SIMULATE transmitting the FAX. DO NOT actually press any buttons on the FAX machine.
- d. This JPM contains time critical elements.
- e. A pre-job brief is not required.
Read Notes prior to giving JPM to student - The Evaluator MUST enter the following Dates and Times on the Notification Form.
- LINE 10 : "DECLARATION" TIME/DATE; use time at which the JPM is started.
DECLARATION TIMEIDATE;
- LINE 12: "Shutdown Time TIMEIDATE; Shutdown at Time" TIME/DATE; use declaration time minus 10 minutes.
- LINE 17: "APPROVAL APPROVAL TimeIDATE";
Time/DATE; use time at which the JPM is started. ALSO FILL IN AN APPROPRIATE TIME/DATE FOR AFFECTED UNIT SHUTDOWN. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) TIME CRITICAL ELEMENT and JPM START TIME UP TO 15 MINUTES NOTE:
- Element 11 shall be simulated
- The time it takes to complete element 2 through 3 is time critical and is required to be completed within 15 minutes of the declaration time which is the start time of the JPM.
- Element 11 can be accomplished after the initial notification.
FNP HLT-33 HLT-33 ADMIN A.4.1.A A.4.1 .A Page 3 of 13 13 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE)
- 1. Initiate the ERO callout system per EIP-8.3 From any plant telephone dial the S/U Table 2 provided by the Shift Manager. number specified on the table to contact the ERO callout system.
prompts that the system would provide: When prompted, the SCENARIO S/U S / U Enter the scenario activation password, "Enter ACTIVATION PASSWORD sign. followed by the pound sign." (123456789) and the SCENARIO you have entered (#entered). Is that correct?
"you ID (87246) from EIP-8.3 Table 2 Enter 9 for yes, or 6 for no no" is entered.
Enter the scenario activation number, followed "Enter S/U S / U sign. by the pound sign." When directed the three (3) key is you have entered (#entered). Is that correct?
"you pushed.
Enter 9 for yes, or 6 for no no" scenario press 33 to build the scenario" "press The security tower called (Cue. "The and indicated that their pager the scenario is building "the building" activated with 800-204-8196, and that the ERO callout system called and delivered message 3".3.
*2. Verify the Southern LINC ENN Radio Red light on power supply is lit S/U being used is turned on and radio is actually turned on.
CAUTION: ** Ensure that no actual transmissions to emergency agencies occur occur.. o WIDE AREA, TRN ENN should be used in lieu of "WIDE WIDE AREA, FEP ENN" ENN
- 3
- 3. Initiate initial notifications using the Press group pushbutton, verify S / U Emergency Notification Network (ENN). display shows WIDE AREA, TRN ENN. An Instructor will be on the other Southern LINC ENN Radio.
See below for student announcement. Press PTT, wait for the chirp and announce "This This is name/title at Farley Nuclear Plant. Please obtain a GENERAL EMERGENCY RED initial notification form and monitor the ENN." ENN. Release the PTT pushbutton. TIME CRITICAL ELEMENT STOP TIME When the candidate presses the PTT pushbutton and says the above statement, the time will be recorded as the stop time.
FNP HLT-33 FNP HL T-33 ADMIN ADMIN A.4.1.A A.4.1.A Page 44 of Page of 13 13 EVALUATION CHECKLIST CHECKLIST RESULTS: RESULTS: ELEMENTS: STANDARDS: STANDARDS: (CIRCLE) (CIRCLE)
*4
*4. Contact ONE Alabama State State Agency. Contact one of the Alabama StateState I U SS/U Agencies listed on Guideline 11 form. When the candidate asks for the first state agency in each category the instructor will say the following:
"Alabama Radiation Control at Montgomery EOC acknowledges manning the ENN).
(CUE: Alabama ENN"). When asked, the INSTRUCTOR will say, John "John Brown is on the line. line."
*5*
*5. Contact ONE Georgia State Agency. Contact with the Georgia State SS /I U Agencies listed on Guideline 1 I form is attempted until one agency acknowledges.
"GEMA acknowledges manning the ENN, Ed Stern is on the line.)
(CUE: GEMA line.")
*6. Contact Houston County. Contacts Houston County per SS /I U Guideline 1 1 form.
Houston County acknowledges manning the ENN, Steve Smith is on the line."). (CUE: "Houston line.).
*7 *7. Contact Early County. Contacts Early County per S / U S/U Guideline 11 form Early County acknowledges manning the ENN, Chuck Tew is on the line.").
(CUE: "Early line.).
- 8. Fill in the date and time on line 2 using the The correct date and time are S I U time that the first state agency contact entered on the Guideline 1I form.
ATTEMPT A TTEMPT was made.
- 9. Conduct pre-message announcement. Initial notification preparation S I/ U message is read per Guideline 11 form, step U. See below:
"Please Please prepare to receive a GENERAL EMERGENCY, RED initial notification message with acknowledgment" acknowledgment
- 10.
1O. Slowly read initial notification message Guideline 11 form read. The S / U SIU over the ENN. following is the REQUIRED minimum information to be read. 11 A DRILL Message # 001 S / U S/U 2 A INITIAL S/U S/U 4 D General Emergency RGI RG1 S / U S/U 5 B Evacuate A B-5 C-5 J-5 S / U S/U K-5
FNPHLT-33ADMIN FNP HLT-33 ADMIN A.4.1.A AA.1.A Page5ofl3 Page 5 of 13 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: STANDARDS: (CIRCLE) (CIRCLE) D D Advise Remainder of ofEPZ Local EPZ to Monitor Local SS /I U Stations/ TARs for Additional Radio/TV Stations! CONSIDER THE Information and CONSIDER THE USE OF KI USE OF IODIDE) IN (POTASSIUM IODIDE) IN ACCORDANCE WITH WITH STATE STATE PLANS AND PLANS AND POLICY. POLICY. 6 B is Occurring SS I U 77 C Above normal operating limits SS /I U 88 B Stable S/U S I U 99 wind direction from 335 degrees SS /I U wind speed A 3.4 mph precipitation none stability class ~ E 10 A declaration time Date - - - 5S /I U Whatever is written 11 Affected unit(s) unite s) 11 S /I U
- 12 and 13 is not r&iuired required to be read 17 approved by W.T. DOOR, Emergency SS /I U Director, and read Time and Date
- 11.11. Verify acknowledgment from Alabama Alabama Radiation Control at S I/ U Radiation Control at Montgomery EOC and Montgomery EOC and GEMA GEMA. questioned regarding receipt of initial notification message. (CUE:
Alabama Radiation Control at "Alabama Montgomery EOC and GEMA acknowledge receipt of initial message). notification message").
- 12. Verify acknowledgment from Houston Houston County and Early County S I U County and Early County questioned regarding receipt of initial notification message. (CUE:
Houston County and Early "Houston County acknowledge receipt of message). initial notification message"). The below action is to be simulated only.
- 13. Fax a copy of the Guideline 11 form to the Guideline 11 form transmitted to S I/ U state of Florida. Florida using speed dial button number 10. (CUE: "The The fax machine sends the form to Florida).
Florida").
FNP HLT-33 HLT-33 ADMIN A.4.1.A Page 66 of 13 13 CHECKLIST EVALUATION CHECKLIST RESULTS: RESULTS: ELEMENTS: STANDARDS: (CIRCLE)
- 14. After receiving the fax report, Verify the Contacts the State of Florida to SS / U state of Florida received the fax. confirm receipt of the Guideline 11 form (CUE: Florida acknowledges receipt of the form).
STOP TIME Terminate JPM when initial notification message is faxed to Florida and the ERO callout has been accom lished. accomplished. CRITICAL ELEMENTS: Critical Elements are denoted with an Asterisk (*) (*) preceding the element number. GENERAL
REFERENCES:
- 1. FNP-0-EIP-8.3 version 12 FNP-O-ETP-8.3
- 2. FNP-0-EIP-9.0 Guideline 1, GENERAL EMERGENCY RED INITIAL NOTIFICATION FNP-O-EIP-9.O FORM version 60
- 3. KAs: G2.4.43 RO-3.2 SRO-3.8 GENERAL TOOLS AND EQUIPMENT:
None COMMENTS:
FNPHLT-33ADM(N FNP HLT-33 ADMIN AA.1.A A.4.1.A Page7ofl3 Page 7 of 13 SOUTHERN LINC Phone talker communication GUIDE Give this to the Instructor performing phone talker duties Alabama Radiation Control at Montgomery EOC acknowledges manning the ENN").
- 4 (CUE: "Alabama ENN).
When asked, the INSTRUCTOR will say, "John John Brown is on the line." line. line.) GEMA acknowledges manning the ENN, Ed Stern is on the line.")
- 5 (CUE: "GEMA line.).
Houston County acknowledges manning the ENN, Steve Smith is on the line.").
- 6 (CUE: "Houston line.).
Early County acknowledges manning the ENN, Chuck Tew is on the line.").
- 7 (CUE: "Early Alabama Radiation Control at Montgomery EOC and GEMA acknowledge receipt of
- 11 (CUE: "Alabama message).
initial notification message"). Houston County and Early County acknowledge receipt of initial notification message").
- 12 (CUE: "Houston message).
- 14 (CUE: Florida acknowledges receipt of the form).
FNP HLT-33 ADMIN FNP HLT-33 ADMIN A.4.1 AA.1.A .A Page 11 of Page of 11 CONDITIONS When II tell When tell you you to to begin, you are begin, you are to to make make initial initial notifications as required for an notifications as emergency and an emergency and activate the activate the emergency emergency callout The conditions under system. The callout system. under which which this task is this task is to be performed to be performed are: are:
- a. A General Emergency has just Shift Manager due to an event on Unit 1.
just been declared by the Shift 1.
- b. The Shift Manager has handed you EIP-8.3, EIP-9.0, Guideline 1, EIP-8.3, Table 2, and EIP-9.O, 1, GENERAL EMERGENCY EMERGENCY RED INITIAL NOTIFICATION FORM.
- c. The Shift Manager has directed you to:
- PERFORM the initial ENN notification over the Southern Southern LINC ENN.
- USE the SOUTHERN LINC and actually perform this function.
- The SOUTHERN LINC will be selected to WIDE AREA TRN ENN on the display.
- ACTIVATE the ERO callout system per EIP-8.3, Table 2.
- SIMULATE the phone call. DO NOT actually press any buttons on the telephone.
- If a FAX is required, SIMULATE transmitting the FAX. DO NOT actually press any buttons on the FAX machine.
- d. This JPM contains time critical elements.
- e. A pre-job brief is not required.
04/05/2010 05:30:00 FNP-0-EIP-8.3 FNP-O-EI P-8. 3 Table 2 rNFORMA TION FOR EMERGENCY RESPONSE NOTIFICATION SYSTEM ACTIVATION INFORMATION
- 1. Obtain the SCENARIO ACTIVATION PASSWORD and the SCENARIO IDENTIFICATION NUMBERS from the Unit 2 Shift Supervisor, the SAS Operator, or the Security Shift Foreman.
123456789 PASSWORD: _ _ _ _ _ _ _ __ SCENARIO ACTIVATION PASSWORD:__________________
- 2. Operations Shift Superintendent, Shift Supervisor (Emergency Director) determine the message to be sent from step 10.
Message Number: _____ 3__ SCENARIO IDENTIFICATION NUMBER: _ _ _ 87246__ 8_7_2_4_6
- 3. Call the Farley Emergency Callout System in Dothan at 9-702-2548 and follow the phone instructions to activate a scenario. If the Farley Emergency Callout System cannot be activated at this number then, go to step 9 to activate the backup system.
- 4. When the system requests it, input the SCENARIO ACTIVATION PASSWORD obtained in step 11 and the SCENARIO IDENTIFICATION NUMBER associated with the message number determined in step 2.
- 5. When directed press the three key on the phone to activate the scenario.
- 6. When the system informs you that the scenario is building hang up the phone.
- 7. If there was a problem activating the Farley Emergency Callout System then, go to step 9 to activate the backup system.
- 8. When the Farley Emergency Callout System or the backup activates, the following will occur:
8.1 Emergency Response Organization pagers will be activated with the (SOO) (800) number. 8.2 The SFM in the SAS should call the Shift Clerk when the ERO pager activated. 8.3 The system will call the Shift Clerk. The call from the SAS and this phone call allows verification that the system has activated. 8.4 For eight to ten minutes, the system will accept calls from individuals that have called in from the pager activation. 8.5 After eight to ten minutes the system will continue to accept inbound calls and will also call all of the individuals in the database that have not responded to the 800 number. 8.6 S.6 As individuals call in or are called, they will have to identify themselves by entering their employee number, receive the message selected in step 2, respond if they are coming to the plant and enter the number of minutes if they are coming to the plant TABLE 2 Page 1 of 2 Version 12
04/05/2010 05:30:00 FNP-0-EIP-8.3 FNP-O-EIP-8.3 Table 2 8.7 Every 15 minutes for the duration of the callout, a printout will be sent to the Shift Clerks office and/or the fax machine in the TSC listing the people that have responded.
- 9. If the system has failed to activate, call the backup system at (800) 475-9705. Enter the company ID code of 1044 and proceed as described in steps 4 through 7.
- 10. If both systems have failed to activate, proceed to FNP-0-EIP-8.3, step 11, to manually Ifboth callout the emergency response staff.
- 11. Message Numbers Message 11 EMERGENCY CALL OUT 999911 9 911 Scenario Identification Number:_________________________
Number: _ _ _ _ _ _ _ _ __ THIS IS NOT A DRILL, I repeat THIS IS NOT A DRILL. This is a call-out of the Farley Emergency Response Organization due to a declared emergency. Respond to your Emergency Response Facility as quickly and safely as possible. THIS IS NOT A DRILL. Message 2 SECURITY EVENT CALL OUT 5 4 321 Scenario Identification Number:________________________ Number: _ _ _ _ _ _ _ _ __ THIS IS NOT A DRILL, I repeat THIS IS NOT A DRILL. This is a call-out of the Farley Emergency Response Organization. An emergency has been declared at the plant due to a security event. If responding from off site, the TSC staff should respond to the Emergency News Center in Dothan as quickly and safely as possible. If you are currently on site, do report to your emergency response facility. Follow the not try to leave the plant or repoli directions issued over the plant public address system. THIS IS NOT A DRILL Message 33 DRILL CALL OUT Number: ---------- 87246 Scenario Identification Number:________________________ THIS IS A DRILL, I repeat THIS IS A DRILL. This is a call-out of the Farley Emergency Response Organization due to a drill or exercise. Respond to your Emergency Response Facility as quickly and safely as possible. THIS IS A DRILL Message 4 COMMUNICATIONS TEST 1119 9 Scenario Identification Number:________________________ Number: _ _ _ _ _ _ _ _ __ THIS IS A DRILL, I repeat THIS IS A DRILL. This is a communication test of the Farley Emergency Response Organization. An emergency classification has not been declared. There is no required activation. Do not physically report to your designated Emergency Response Facility. This is a communication test only. THIS IS A DRILL. TABLE 2 Page 22 of 2 Version 12
04/05/2010 05:30:00 FNP-0-EIP-9.0 GUIDELINE 1 I GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM 1 1DRILLDRILL I§] JACTUAL ACTUAL EVENT MESSAGE /JOI 2 INITIAL 2@INITIAL NOTIFICATION: TIME_ _ _ _ _ DATE_-'-_-'--_.AUTHENTICATION DATE / / AUTHENTICATION#NIA # N/A (334) 814-4662, 814-4663
- 3. SITE: FARLEY NUCLEAR PLANT Confirmation Phone # (334) 794-0800, 899-5156 (ext 4662, 4663)
- 4. EMERGENCY CLASS CLASS~ION: ION: (JJ)3ENERAL EMERGENCY BASEDONEAL#__________
BASED ON EAL # t{l.;il
- 5. PROTECTIVE ACTION RECOMMENDATIONS:
VACUATE
@=VACUATE LC 19 jj SHELTER @ Advise Remainder of EPZ to Monitor Local Radio/TV Stations/ TARs for Additional Information and CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POLICY.
OTHER _____________________~~____________________________________
~OTHER
- 6. EMERGENCY RELEASE: ~ None Occurring 19 Has Occurred
- 7. RELEASE SIGNIFICANCE: ~ Not applicable I§] Within normal bove C bove normal IQ]
J Under operating limits operating limits evaluation
- 8. EVENT PROGNOSIS: ~
j Improving tabIe
@>table 19 Degrading
- 9. METEOROLOGICAL DATA: Wind Direction from .degrees 335degreeS Wind Speed 3 m 4
_ 4
. ph mPh 35 foot elevation preferred Precipitation I<<J#ee Sbility Class §I Stability j @I L1 19 EJ 1 D El
[Q] 110O~ECLARATION ECLARATION Time ____________ Date _ _..:I____./____
- 11. AFFECTED UNIT(S): @ [] 16m
- 12. UNIT STATUS: ~ UiU1 _ _% Power Shutdown at Time declaration time minus 10 minutes Date (Unaffected Unit(s)
Unites) Status Not Required for Today Initial Notifications) @I U2 _ _% Power Shutdown at Time __________ Date _ ,/I ___,___
- 13. REMARKS: No No additional remarks D read additional remarks on separate page 07,
- 17. APPROVED BY: Do Title Emergency Director Time- - - -Date- -/ - -/ -
NOTE: The information that is highlighted on this form must be correct for the notification to be considered correct. A.X-Line II check box A or B. Select B A._Line B only if it is an actual event in the plant B. B.-*Line Line I1 Number each verbal initial and follow-up messages sequentially starting at 001 for the first verbal message. C. Line 2 Notification time to be completed by ENN communicator just prior to making the ENN notification D.~Line 4 Line 4 Enter the (one) highest emergency classification EAL number as listed in EIP-9.2 using the top down left to D._Line right method of evaluation. For example, ifsite if site criteria is met for EAL SA5 5A5 and FAlsimultaneously, FAIFA1 should be listed on line 4. E.Line 55 Refer to NMP-EP-E.-><-Line NMP-EP-I09,109, Protective Action Recommendations to determine appropriate Protective Action Recommendations (PARs). (PARS). Mark box B or C and the appropriate zones for evacuation or sheltering. Box D is pre-marked. Mark and complete box E if PAR 4 is required or there are other PARS beyond NMP-EP-109. NMP-EP-I09. F.~Line 6 An emergency release is occurring if an effluent monitor has increased by a factor of 10 over and above normal operating levels OR is in alarm. The effluent monitors are R-18, R-23B, R-15, R-14, R-22. R-60 (A,B,C,D) and R- R 29B(NG)
** Mark box A if no emergency release is in progress or has occurred
** Mark box B B if an emergency release is in progress
** Mark box C C if an emergency release has occurred, but is currently stopped 6 OF 8 Version 60.0
04/05/2010 04/05/2010 05:30:00 05:30:00 FNP-0-EIP-9.0 FNP-0-EIP-9.0 GUIDELINE I1 GUIDELINE GENERAL EMERGENCY GENERAL EMERGENCY RED VERBAL RED NOTIFICATION FORM VERBAL NOTIFICATION FORM G.~Line 77 Release G.Line Release Significance. Significance. Mark Mark box box A, B, CC or A, B, or D. limits are Normal limits D. Normal are being exceeded if being exceeded if an an effluent effluent monitor listed monitor listed in step FF above in step above is is in in alarm alarm
- Mark box Mark box A if 6A isis marked if 6A marked
** Mark Mark boxbox BB if if 6B 6B or or 6C marked and 6C isis marked and NO effluent monitor isis or NO effluent or has been in has been in alarm.
** Mark Mark boxbox CC if if 6B 6B or or 6C6C isis marked marked and ANY effluent monitor and ANY or has monitor isis or been in has been in alarm.
- Mark box Mark box DD if if 6B 6B or or 6C6C isis marked marked andand itit can can not be determined if be determined effluent monitor isis or if an effluent or has has been in alarm.
been in alarm. H.X-Line 88 Event H.Line Event Prognosis. Prognosis. Mark Mark box box A, A, BB oror C. C.
- AA should should bebe marked if if mitigation mitigation efforts progressing toward termination/recovery.
efforts appear successful, progressing termination/recovery.
** BB should should be be marked marked if if escalation escalation to classification isis unlikely to aa higher classification unlikely based on current based on current conditions.
conditions.
" .* CC should should be marked if escalation be marked escalation to classification or emergency classification to aa higher emergency PAR change isis likely.
or PAR L_" I. __
>< Line 99 Meteorological Line Meteorological Data
- Fill in the meteorological data required Fill in required (35 elevation preferred).
(35 foot elevation preferred).
- When possible use When use 15 available from EP_WEATHER 15 minute average data, available EP_ WEATHER on on the IPC.
IPC.
** If EP _WEATHER. Is not available then use the guidance IfEP FNP-O-EIP-9.3 Data Sheet guidance in FNP-0-EIP-9.3 obtaining meteorological Sheet II for obtaining data.
- If stability class is not available it can be calculated from delta temperature from the below table
~T (200 AT (200' elev. temp, °F OF - 35
- 35' elev. temp, °F) OF) Stability Class
<-1.74 A
-1.74 to <-1.56 B B
-1.56 to <-1.38 C
-l.38
-1.38 to <-0.46 D
-0.46 to<1.38 to < l.38 E l.38 1.38 to 3.60 F
>3.60 G J.
K.
>< Line 10 Time is for the declaration checked in line 4 ~Line 11 Mark the unit that is involved with the emergency declaration, or all if both units are affected.
K<Line L. L.Line Line 12 Fill in the per cent power or the time of shutdown for units involved with the event M.>< MLine Line 13 If additional remarks are required mark the box for additional remarks and write them on a separate
" paper and have them read over the ENN, or mark the box for no additional remarks N._"
N. _ _The Emergency Director must sign the form with time and date. O.
- 0. Within 15 minutes of declaration time, using the ENN contact the state and local agencies listed below.
P. _ _Verify the Southern LINC ENN Radio being used is turned on Q. Q. _ _IftheIf the Southern LINC display does not show "WIDE WIDE AREA, FEP ENN" ENN when group is pressed in step R, THEN perform the following:
- Press the button with the square until the top line is indicated, then press the arrow buttons until "WIDE WIDE AREA" AREA is displayed, then press the button under OK. Press the button with the square until the second line is indicated then press the arrow buttons until "FEP FEP ENN" ENN is displayed, and then press the button under OK.
R ___Press group pushbutton, verify display shows WIDE AREA, FEP ENN. Correct per above step if necessary. Pickup handset or leave in cradle, press to talk (PTT), wait for the chirp and announce "This This is name/title at Farley Nuclear Plant. Please obtain a GENERAL EMERGENCY RED initial notification form and monitor the ENN." ENN. Release the PTT. S. ___ Contact one state and county agency listed in each of the four boxes below. Indicate the time of initial attempt to contact any Alabama agency. Circle agency actually contacted. Indicate the name of the individual contacted. Underlined phone numbers staffed 24 hours a day PTT and request one Alabama agency in the order listed below acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PTT after each request. ALABAMA State Agencies In preferred order
** Alabama Radiation Control at Montgomery EOC. ENN (1305), OPX (6628), (334-206-5391), (334-324-0076)
** AEMA ENN (1306). OPX(6619), (205-280-2312, (205-280-2312. 205-280-2310)
** Alabama Radiation Control at Alabama Forward EOC, ENN (1307), OPX 6621), (334-793-1565)
** HOUSTON COUNTY ENN (1307), (1307). OPX (6621), (334-794-9720, 793-9655, 677-4807, 677-4807. 4808)
Time Time_____Name Name__________.Acknowledged Acknowledged
04/05/2010 04/05/2010 05:30:00 05:30:00 FNP-0-EIP-9.0 FNP-0-EIP-9.0 GUIDELINE I1 GUIDELINE GENERAL EMERGENCY GENERAL EMERGENCY RED VERBAL RED NOTIFICATION FORM VERBAL NOTIFICATION FORM Indicate the Indicate the time time of of initial initial attempt attempt to contact any to contact any Georgia agency. Circle Georgia agency. agency actually Circle agency actually contacted. Indicate the contacted. Indicate the name name of the ofthe individual contacted. individual contacted. Underlined Underlined phone phone numbers numbers staffed staffed 2424 hours hours aa day day PTT and PTT and request one one Georgia agency agency inin the the order listed below order listed acknowledge manning of below acknowledge the ENN. State of the agency name and State agency and if they are on ask if on the line. line. Release Release the PTT after each the PTT each request. request. GEORGIA State State Agencies In In preferred order
- GEMAGEM A at Atlanta Atlanta EOC, ENN ENN (1304), OPX (6629), (404-635-7200)
OPX (6629). (404-635-7200)
- GEMAGEMA at Georgia Forward Forward EOC, ENN (1308) OPX OPX (6626), (229-723-4826)
(229-723-4826)
- EARLY COUNTY, COUNTY, ENN(1308)
ENN(1308) OPX OPX (6622),(229-723-3577, 3578, 3578, 4826) 4826) Time_ _ _ _Name_ _ _ _ _ _ _ _ _ _Acknowledged LI0 Indicate the time of initial attempt to contact Houston County. Indicate the name of the individual contacted. Underlined phone numbers staffed 24 hours a day PTT and request Houston County acknowledge manning of the ENN. State agency name and ask if ofthe they are on the line. ifthey Release the PTT after each request. HOUSTON COUNTY
- HOUSTON COUNTY, ENN(1307), ENN(l307), OPX (6621), (334-794-9720, 793-9655, 334-677-4807, 4808)
Time_ _ _ _Name _ _ _ _ _ _ _ _ _ _Acknowledged 0 LI Indicate the time of initial attempt to contact Early County. Indicate the name ofthe of the individual contacted. Underlined phone numbers staffed 24 hours a day PTT and request Early County acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PTT after each request. EARLY COUNTY
- EARLY COUNTY, ENN(l308) ENN(1308) OPX (6622), (229-723-3577, 3578, 4826)
Time_ _ _ _Name, Name_ _ _ _ _ _ _ _ _ _Acknowledged 0LI T. _ _Fill in the date and time on line 2 using the time that the first state agency contact ATTEMPT was made U. _ _PTT and announce on the ENN "Please Please prepare to receive a GENERAL EMERGENCY, RED initial notification message with acknowledgment", acknowledgment, then slowly read the GE initial notification form over the ENN. Release the PTT after reading two or three lines to allow individuals to respond. V. _ _Have the agencies contacted above, acknowledge receipt of the message and fill in the acknowledge checkbox above when they do. W. _ _If any required agency could not be contacted on the ENN, then use numbers listed with each agency or in W.If FNP-0-EIP-8. 1 to contact them by any available means as soon as possible. FNP-0-EIP-8.1 X X Fax a copy of the previous page GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM to the State of Florida, EOF using speed dial #10 Y. _ _Wait for the Fax report indicating the fax was received then verify verif, the state of Florida has received the Fax by calling. (800-320-0519) (850-413- 9911) 8 OF 8 Version 60.0}}