Text

Initial Exam 2010-301 Final Administrative JPMs (Section 12)
	ML101650639
Person / Time
Site:	Farley
Issue date:	06/07/2010
From:	; NRC/RGN-II
To:	; Southern Nuclear Operating Co
References
	Download: ML101650639 (106)
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{{#Wiki_filter:FNP HLT-33 ADMIN Page 1 of 10 A.1.1.A Conduct of Operations ADMIN G2.1.40 RO & SRO A.1.1.A TITLE: Verification of Initial Conditions Prior to Core Alterations. PROGRAM APPLICABLE: SOT SOCT OLT X LOCT____ ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 30 MN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL 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, if any. Examinee: Overall JPM Performance: Satisfactory E1 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary) EXAMINER: Developer H. Fitzwater 2/09/10 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP HLT-33 ADMIN Page 1 of 10 A.1.1.A Conduct of Operations ADMIN G2.1.40 - RO & SRO A. 1. l.A TITLE: Verification ofInitial Conditions Prior to Core Alterations. PROGRAM APPLICABLE: SOT SOCT OL T.-lL LOCT __ ACCEPTABLE EVALUATION METHOD: ~ PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM ~ CLASSROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL 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. Examinee: Overall JPM Performance: Satisfactory 0 Unsatisfactory 0 Evaluator Comments (attach additional sheets if necessary) EXAMINER: ________________ _ H. Fitzwater 2/09/10 SEE NUREG 1021 FORM ES-301-3

FNPHLT-33ADMIN A.1.1.A Page2oflO CONDITIONS When I tell you to begin, you are to perform or evaluate all steps FNP-1 -UOP-4. 1, Appendix 6, Verification of Initial Conditions Prior to Core Alterations. The conditions under which this task is to be performed are: a. Core Offload was suspended 18 hours ago. b. RCS temp is 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 been verified available 10 minutes ago. 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 request. h. FNP1-STP-1 8.4, Containment Midloop and/or Refueling Integrity Verification and Containment Closure, was completed yesterday at 1400. i. 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. o. Identify all initial conditions for core alterations listed in UOP-4.1, Appendix 6, which are not satisfied, if any. INITIATING CUE: 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 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 the Reactor Cavity verified within one hour.

completed. Utilizes initial conditions to verify task complete. 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). FNP HLT-33 ADMIN A.1.1.A Page 2 of 10 CONDITIONS When I tell you to begin, you are to perform or evaluate all steps FNP-I-UOP-4.1, Appendix 6, Verification of Initial Conditions Prior to Core Alterations. The conditions under which this task is to be performed are:

a. Core Offload was suspended 18 hours ago.

b. RCS temp is 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 been verified available 10 minutes ago.

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 chemistry's request.

h. FNP-I-STP-18.4, Containment Midloop andlor Refueling Integrity Verification and Containment Closure, was completed yesterday at 1400.

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-I-UOP-4. 1, Appendix 6.

o. Identify all initial conditions for core alterations listed in UOP-4.1, Appendix 6, which are not satisfied, if any.

INITIATING CUE: "You may begin." EVALUATION CHECKLIST ELEMENTS: START TIME

1. (STEP 2.1 & 2.2) Checks correct version and conducted on appropriate unit.

2. (STEP 3.1) Communications between MCR and the Reactor Cavity verified within one hour.

STANDARDS:

1) Determines step 2.1 & 2.2 has been completed. Utilizes WebTop and verifies unit from initial conditions

2) Determines step 3.1 has been completed. Utilizes initial conditions to verify task complete.

RESULTS: (CIRCLE) S/U S/U 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).

FNP HLT-33 ADMIN A.1.1.A Page 3 of 10 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 3. (STEP 3.2.1) Verify N-3 1, Source Range NI,

3) Determines step 3.2.1 has been S / U detector operable.

satisfied; Utilizes picture of N-31 and determines that the instrument is operable. (reference SOP-39.0 section 4.1)

a. Check N-3 I 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 ii.Operation Selector ii. Normal iii.High Flux at shutdown iii. Normal c. Perform a channel check per STP-1.0 (SR

c. Acceptable per STP-1.0 3.9.2.1).

allowances 4. (STEP 3.2.2)Verify N-32, Source Range NI,

4) Determines step 3.2.2 can not S / U detector operable.

be satisfied; Utilizes picture of N-32 and determines that the instrument is NOT operable. (reference 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 ii.Operation Selector ii. Normal iii.High Flux at shutdown iii. Normal

c. Performs a channel check per STP-1.0 (SR

c. NOT Acceptable per STP 3.9.2.1).

1.0 allowances. FNP HL T-33 ADMIN EVALUATION CHECKLIST ELEMENTS: A.1.1.A

3. (STEP 3.2.1) Verify N-31, Source Range NI, detector operable.

(reference SOP-39.0 section 4.1)

a. Check N-31 Instrument power on AND control power on lights illuminated.

b. Check switches aligned:

i. Level Trip ii.Operation Selector iii.High Flux at shutdown

c. Perform a channel check per STP-1.0 (SR 3.9.2.1).

4. (STEP 3.2.2)Verify N-32, Source Range NI, detector operable.

(reference SOP-39.0 section 4.1)

a. Check N-32 Instrument power on AND control power on lights illuminated.

b. Check switches aligned:

i. Level Trip ii.Operation Selector iii.High Flux at shutdown

c. Performs a channel check per STP-1.0 (SR 3.9.2.1).

Page 3 of 10 RESULTS: STANDARDS: (CIRCLE)

3) Determines step 3.2.1 has been S I U satisfied; Utilizes picture ofN-31 and determines that the instrument is operable.

a. lights are illuminated

b. Switches are in position:

I. Normal

11. Normal Ill. Normal

c. Acceptable per STP-1.0 allowances

4) Determines step 3.2.2 can not S I U be satisfied; Utilizes picture of N-32 and determines that the instrument is NOT operable.

a. Lights are checked Instrument power light is NOT illuminated.

Control power is illuminated.

b. Switches are determined; I. Normal ii. Normal iii. Normal

c. NOT Acceptable per STP-1.0 allowances.

FNP HLT-33 ADMIN A.1.1.A Page 4 of 10 EVALUATION CHECKLIST ELEMENTS: 5. (STEP 3.2.3)Verify N-48, Gamma-metrics Source Range NI, detector operable. (reference SOP-39.0 section 4.3) a. Checks N-48 in service. b. Performs a channel check per STP-1.0 (SR 3.9.2.1). STANDARDS:

5) Determines step 3.2.3 has been satisfied. (May identify that the Refueling Coordinator must first be consulted.)

a. Aligned and in service as indicated by picture and bulleted items listed on picture. b. Acceptable per STP-l.0 Table 1 allowances. RESULTS: (CIRCLE) S/U

6) Determines step 3.3 has been S / U satisfied; Utilizes initial conditions to verify boron concentration.

(

Reference:

SOP-45.0 section 4.1.3 TRIVI 13.3.4) a. Verify Operation Selector switch position. b. Verify Range Selector switch position. c. Verify Drawer indication lights: i. Power ii. Channel Test light iii. High Alarm iv. Low Alarm

7) Identifies R-5 is NOT operable/operating; Determines step 3.4.1 has NOT been satisfied. (May annotate failure or need to initiate survey).

a. Level Cal. b. WIDE c. Lights are: i.ON ii. ON iii. OFF 6. (STEP 3.3) Reactor Coolant system 2000 ppm. NOTE: Element 7 would require either R-5 being in service OR required action being taken. The 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 SS acknowledges the issue you have identified and directs you to continue. No compensatory actions have yet been completed. 7. (STEP 3.4.1) Verifies R-5 operable/operating. S / U iv. OFF FNP HLT-33 ADMIN EVALUATION CHECKLIST ELEMENTS: S. (STEP 3.2.3)Verify N-48, Gamma-metrics Source Range NI, detector operable. (reference SOP-39.0 section 4.3)

a. Checks N-48 in service.

A.1.1.A

b. Performs a channel check per STP-1.0 (SR 3.9.2.1).

6. (STEP 3.3) Reactor Coolant system 2000 ppm.

Page 4 of 10 RESULTS: STANDARDS: (CIRCLE)

5) Determines step 3.2.3 has been S / U satisfied. (May identify that the Refueling Coordinator must first be consulted.)

a. Aligned and in service as indicated by picture and bulleted items listed on picture.

b. Acceptable per STP-1.0 Table 1 allowances.

6) Determines step 3.3 has been satisfied; Utilizes initial conditions to verify boron concentration.

S/U NOTE: Element 7 would require either R-S being in service OR required action being taken. The 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 SS acknowledges the issue you have identified and directs you to continue. No compensatory actions have yet been completed."

7. (STEP 3.4.1) Verifies R-S operable/operating.

(

Reference:

SOP-4S.0 section 4.1.3; TRM 13.3.4)

a. Verify Operation Selector switch position.

b. Verify Range Selector switch position.

c. Verify Drawer indication lights:

i.

Power

11.

Channel Test light 111. High Alarm IV. Low Alarm

7) Identifies R-S is NOT S / U operable/operating; Determines step 3.4.1 has NOT been satisfied. (May annotate failure or need to initiate survey).

a. Level Cal.

b. WIDE

c. Lights are:

1. ON ii. ON 111. OFF IV. OFF

FNPHLT-33ADMIN A.1.1.A Page5oflO EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE)

8. (STEP 3.4.2 through 3.4.4) Verifies R-24AorB,

8) Identifies radiation monitors are S / 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 ii. Pump Power ii. ON iii. Pump Start iii. Start/Neutral d. Verify MCR lights:

d. MCR lights are:

i. Power light i. ON ii. Pump ON light ii. ON iii. Flow fault light iii. OFF iv. Alert light iv. OFF v. High light v. OFF vi. Fail/Reset light vi. ON vii. Poweron light vii. ON 9. (STEP 3.5 through 3.6) Evaluates Refueling

9) Utilizes initial conditions and S / U integrity has been verified within 100 hrs, and that evaluates that step 3.5 is 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: Identify all, if any, initial conditions listed in UOP-4.1, Appendix 6 which are not satisfied. 10.Reports/annotates that step 3.2.2 and 3.4.1 are not

10) Identifies N32 inoperable, R-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. FNP HL T-33 ADMIN EVALUATION CHECKLIST ELEMENTS: A.1.1.A

8. (STEP 3.4.2 through 3.4.4) Verifies R-24AorB, R-25AorB, and R-35AorB operable using SOP-45.0 section 4.1.5.

(uses pictures of LOCAL radiation monitor indications to determine the following conditions)

a. Verify local switch for vacuum pump.

b. Verify LOCAL switch position.

(uses pictures of radiation monitor drawers to determine the following conditions)

c. Verify MCR switch:

d.

i.

Operation selector

11.

Pump Power Ill. Pump Start Verity MCR lights:

i.

Power light

11.

Pump ON light Ill. Flow fault light IV. Alert light

v.

High light vi. Fail/Reset light VII. Power on light

9. (STEP 3.5 through 3.6) Evaluates Refueling integrity has been verified within 100 hrs, and that step 3.6 is not applicable.

Page 5 of 10 RESULTS: STANDARDS: (CIRCLE)

8) Identifies radiation monitors are S / U operable; Initials step 3.4.2 through 3.4.4.

The following indications are for all steps 3.4.2 through 3.4.4:

a. AUTO

b. ON (and Fans are running)

c. MCR switches are:

1.

Oper

11.

ON iii. StartlNeutral

d. MCR lights are:

1.

ON

11. ON Ill. OFF IV. OFF

v. OFF vi. ON VII. ON

9) Utilizes initial conditions and evaluates that step 3.5 is satisfied and 3.6 in N/A.

S/U NOTE: REVIEW of completed Appendix 6 to evaluate the above elements. CUE: Identify all, if any, initial conditions listed in UOP-4.l, Appendix 6 which are not satisfied.

10. Reports/annotates that step 3.2.2 and 3.4.1 are not completed or satisfied and that core Alts initial conditions are not satisfied.

10) Identifies N32 inoperable, R-5 inoperable and that Core alterations should not be permitted since the initial conditions have not been satisfied.

S/U

FNPHLT-33ADMIN A.1.1.A Page6oflo 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 Audio Counts.

IMMEDIATELY verify un borated water sources are isolated.

12. Evaluates TRM 13.3.4 condition B.

12) Identifies the need to S / U 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 range neutron flux monitor inoperable.

Condition A for N32 inoperable 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 ADMIN EVALUATION CHECKLIST ELEMENTS:

A.1.1.A STANDARDS: Page 6 of 10 RESULTS: (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 Audio Counts.
12. Evaluates TRM 13.3.4 condition B.

13. Evaluates TS 3.9.2 Condition A: One source range neutron flux monitor inoperable.

11) Identifies the need to S / U IMMEDIATELY verify un-borated water sources are isolated.

12) Identifies the need to S / U IMMEDIATELY notify HP to perform a survey of the SFP area within 24 hours.

13) Identifies an ADMIN LCO for S / U 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 G2.1.36 G2.1.32 2.8 3.9 3.0 4.1 3.8 4.0

FNP HLT-33 ADMIN A.1.1.A Page 7 of 10 GENERAL TOOLS AND EQUIPMENT: 1. References to be accessed via classroom computer (using exam ID logon) and Exam Reference disk/files only. 2. Provide UOP-4. 1, Appendix 6 3. Pen/pencil 4. Pictures of the following components: (11 pages total) a. R-24A Local indications g. b. R-24B Local indications h. c. R-25A Local indications i. d. R-25B Local indications j. e. R-35A Local indications k. f. R-35B Local indications 1. Critical ELEMENT justification: STEP Evaluation R24A & R25A MCR indications R-24B & R25B MCR indications R-35A & R35B MCR indications N3 1 drawer indications N32 drawer indications N3 1, N32 & N48 Board indications

m. Audio Count Rate Channel Drawer NOTE:

The listed sub-steps to each element (a.b.c...) describe the anticipated actions taken by the candidate. Completion 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. NOT criticalthis step is for satisfying site procedural protocol and expectations. 2. NOT critical this step is for satisfying site level expectations or requirements. 3. NOT criticalAlthough Task objective-component is operable. 4. Critical Element Task objective-evaluate operability of required equipment. 5. NOT criticalAlthough Task objective-component is operable. 6. NOT critical this step does not require any evaluation from the candidate. 7. Critical Element Task objective-evaluate operability of required equipment. 8. NOT criticalAlthough Task objective-components are operable. 9. Critical ElementFINAL Task objective-identifies that initial conditions are not satisfied for Core Alts. 10. NOT critical this step does not require any evaluation from the candidate. SRO Critical ElementIDENTIFIES and IMPLEMENTS the Actions for License requirement. 11. SRO Critical ElementIDENTIFIES and IMPLEMENTS the Actions for License requirement. 12. SRO 13. NOT criticalAdministrative LCO is for tracking purposes only. FNP HL T-33 ADMIN A.1.1.A Page 7 of 10 GENERAL TOOLS AND EQUIPMENT:

1. References to be accessed via classroom computer (using exam ID logon) and Exam Reference disk/files only.

2. Provide UOP-4.I, Appendix 6

3. Pen/pencil

4. Pictures of the following components: (11 pages total)

a. R-24A Local indications

b. R-24B Local indications

c. R-25A Local indications

d. R-25B Local indications

e. R-35A Local indications

f.

R-35B Local indications

g. R24A & R25A MCR indications

h. R-24B & R25B MCR indications

i.

R-35A & R35B MCR indications J. N3I drawer indications

k. N32 drawer indications

1.

N3I, N32 & N48 Board indications

m. Audio Count Rate Channel Drawer Critical ELEMENT justification:

NOTE:

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

SRO

11.

SRO

12.

SRO

13.

Evaluation The listed sub-steps to each element (a.b.c... ) describe the anticipated actions taken by the candidate. Completion 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. NOT critical-this step is for satisfying site procedural protocol and expectations. NOT critical-this step is for satisfying site level expectations or requirements. NOT critical-Although Task objective-component is operable. Critical Element -Task objective-evaluate operability of required equipment. NOT critical-Although Task objective-component is operable. NOT critical - this step does not require any evaluation from the candidate. Critical Element -Task objective-evaluate operability of required equipment. NOT critical-Although Task objective-components are operable. Critical Element-FINAL Task objective-identifies that initial conditions are not satisfied for Core Alts. NOT critical-this step does not require any evaluation from the candidate. Critical Element-IDENTIFIES and IMPLEMENTS the Actions for License requirement. Critical Element-IDENTIFIES and IMPLEMENTS the Actions for License requirement. NOT critical-Administrative LCO is for tracking purposes only.

FNP HLT-33 ADMIN A.1.1.A Page 8 of 10 COMMENTS: References expected to be utilized: STP-1.0, section 5.22, Table 1 of Appendix 1 and Appendix 3, Ver. 98.0; channel check information M-50 Master list of Surveillance Tests, Ver. 25.0; determine channel check procedure SOP-3 9.0, Nuclear Instrumentation System, Ver. 9.0; evaluate switch alignrnent/operabi lity SOP-45.O, Radiation Monitoring System, Ver. 36.0; evaluate switch alignment/operability TRM 13.3.4 Ver 8.0, and Basis Ver 3.0. TS 3.9.2 and Basis, Amendment 146 (U-i), Amendment 137 (U-2) UOP-4.1, CONTROLLING PROCEDURE FOR REFUELING, Ver. 52.0 [C) DISC;USS with the examiner: Due 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 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 ofNON-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 metrics must be evaluated as coupled by Refueling Coordinator. FNP HL T-33 ADMIN COMMENTS: References expected to be utilized: A.1.1.A Page 8 of 10 STP-1.0, section 5.22, Table 1 of Appendix 1 and Appendix 3, Ver. 98.0; channel check information M-50 Master list of Surveillance Tests, Ver. 25.0; determine channel check procedure SOP-39.0, Nuclear Instrumentation System, Ver. 9.0; evaluate switch alignment/operability SOP-45.0, Radiation Monitoring System, Ver. 36.0; evaluate switch alignment/operability TRM 13.3.4 Ver 8.0, and Basis Ver 3.0. TS 3.9.2 and Basis, Amendment 146 (U-I), Amendment 137 (U-2) UOP-4.I, CONTROLLING PROCEDURE FOR REFUELING, Ver. 52.0 '1'0 DISCUSS with the examiner: Due 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, 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 metrics must be evaluated as coupled by Refueling Coordinator.

FNP HLT-33 ADMIN HANDOUT #2 Page 1 of I 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 HLT-33 ADMIN HANDOUT #2 Page 1 of 1 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.

FNPHLT-33ADMIN A.1.1.A HANDOUT Page 1 of 1 CONDITIONS When I tell you to begin, you are to perform or evaluate all steps FNP-1-UOP-4.1, Appendix 6, Verification of Initial Conditions Prior to Core Alterations. The conditions under which this task is to be performed are: a. Core Offload was suspended 18 hours ago. b. RCS temp is 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 been verified available 10 minutes ago. 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 request. h. FNP-1-STP-18.4, Containment Midloop and/or Refueling Integrity Verification and Containment Closure, was completed yesterday at 1400. i. 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. o. Identify all initial conditions for core alterations listed in UOP-4. 1, Appendix 6, which are not satisfied, if any. FNP HL T-33 ADMIN A.1.1.A HANDOUT Page 1 of 1 CONDITIONS When I tell you to begin, you are to perform or evaluate all steps FNP-I-DOP-4.1, Appendix 6, Verification of Initial Conditions Prior to Core Alterations. The conditions under which this task is to be performed are:

a. Core Offload was suspended 18 hours ago.

b. RCS temp is 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 been verified available 10 minutes ago.

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 chemistry's request.

h. FNP-I-STP-18.4, Containment Midloop and/or Refueling Integrity Verification and Containment Closure, was completed yesterday at 1400.

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 ofFNP-I-DOP-4.1, Appendix 6.

o. Identify all initial conditions for core alterations listed in DOP-4.1, Appendix 6, which are not satisfied, if any.

12/09/09 14:42:20 FNP1-UOP-4.1 APPENDIX 6 VERIFICATION OF INITIAL CONDITIONS PRIOR TO CORE ALTERATIONS Performed by: Date Reviewed by: Date This appendix consists of 2 pages Version 52.0 12/09/09 14:42:20 APPENDIX 6 VERIFICATION OF INITIAL CONDITIONS PRIOR TO CORE AL TERA TIONS Date FNP-I-UOP-4.1 Performed by: ------------------------ Reviewed by: Date ----------------------- This appendix consists of 2 pages 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 ALTERATIONS

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 / 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 if 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 1 3.2.2 Source Range Nuclear Instrument, Channel N-32 3.2.3 Gamma-Metrics Neutron Flux Monitor, Channel N-48 Page 1 of 2 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 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 _1-The direct communications system between the control room and the reactor 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-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-31 3.2.2 Source Range Nuclear Instrument, Channel N-32 3.2.3 Gamma-Metrics Neutron Flux Monitor, Channel N-48 Page 1 of2 Version 52.0

12/09/09 14:42:20 FNP-1-UOP-4.1 APPENDIX 6 3.3 The reactor coolant system boron concentration is> 2000 ppm. 3.4 The following radiation monitors are in operation per FNP-1-SOP-45.0, RADIATION MONITORING SYSTEM, or required action is being taken per Tech. Specs 3.3.6, 3.3.7, and 3.3.8, and TR 13.3.4. 3.4.1 R-5 Spent fuel storage or portable monitoring instrumentation used to monitor SFP area at least once per 24 hours (for fuel movement in SFP). 3.4.2. R-25A or 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 3.5 Refueling integrity has been verified per FNP-1-STP-18.4, CONTAINMENT / MIDLOOP AND/OR REFUELING INTEGRITY VERIFICATION AND CONTAINMENT CLOSURE within 100 hours prior to the start of core alterations. 3.6 jf the containment equipment hatch, personnel air lock, or auxiliary air lock is 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 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 has been completed by Maintenance within the last seven days Page 2 of 2 Version 52.0 12/09/09 14:42:20 FNP-1-UOP-4.1 APPENDIX 6 _/- _/- MM _/- 3.3 The reactor coolant system boron concentration is:::: 2000 ppm. 3.4 The following radiation monitors are in operation per FNP-1-S0P-45.0, RADIA TION MONITORING SYSTEM, or required action is being taken per Tech. Specs 3.3.6, 3.3.7, and 3.3.8, and TR 13.3.4. 3.5 3.4.1 R-5 Spent fuel storage or portable monitoring instrumentation used to monitor SFP area at least once per 24 hours (for fuel movement in SFP). 3.4.2. R-25A or 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 HV AC Refueling integrity has been verified per FNP-1-STP-18.4, CONTAINMENT MID LOOP AND/OR REFUELING INTEGRITY VERIFICATION AND CONTAINMENT CLOSURE within 100 hours prior to the start of core alterati ons. 3.6 IF the containment equipment hatch, personnel air lock, or auxiliary air lock is 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) 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-O-STP-61 0.0 has been completed by Maintenance within the last seven days Page 2 of2 Version 52.0

NUCLEAR INSTRUMENTATION PROTECTION CHANNEL I SOURCE RANGE xoo / N1C55N10031

WSTRENT PQd!RON IISV, 5A, AC IHSW POWER IIBV,5A,AC CONTROL POWER NUCLEAR INSTRUMENTATION PROTECTION CHANNEll. 118V.5A,AC COf4TROl. POWER

-I C) 1) C) 118V.5A,AC CONTROL POWER

j L_J ) 0> -rn o oP z

MCB instrumentation Gamma Metrics Local indications: I

48A EQ 10 10 10 486 EQ I

100 10 10 10

.10 10 4 10

10 10 o HSDP Excore Neutron Monitor N-48 breaker, QIR2ILOO5A is closed.

o The nonoperate LED is not illuminated. MCB instrumentation Gamma Metrics Local indications: 0 HSDP Excore Neutron Monitor N-48 breaker, 01 R21 L005A is closed. 0 The nonoperate LED is not illuminated.

r power pump on Putnp Functø 4d purge Etop I V*CTc7cIEEN] L. Pump Function fauft

IJT1IE.

pa er off on off norrn prog.

R2E3 CTMT PURGE oprri t of t

aternaier Function Switch cpm vQIC do rOWNY OtVOON 4? \\ R-358 CONT RM PiILET AIR caI hv. off I oper pump powerfli alert c. e pfl

CONT PURGE R-24B LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running. Pump Function Switch CONT PURGE R-24B LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running.

CONT PURGE R-24A LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running. Pump Function Switch CONT PURGE R-24A LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running.

CONT RM AIR SUPPLY R-35A LOCAL INDICATIONS Pump Function Switch CONT RM AIR SUPPLY R-35A LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running.

CONT RM AIR SUPPLY R-35B LOCAL INDICATIONS CONT RM AIR SUPPLY RC R-35B Pump Function Switch CONT RM AIR SUPPLY R-358 LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running.

FUEL BLDG R-25B cp m flOIt5 dc LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running. Pump Function Switch FUEL BLDG R-25B LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running.

TDREN FUEL BLDG R-25A LOCAL INDICATIONS Pump Function Switch FUEL BLDG R-25A LOCAL INDICATIONS OBSERVATION: The cabinet ventilating fans are running.

FNP HLT-33 ADMIN Page 1 of 5 A.1.2.S Conduct of Operations ADMIN G2.1.25 SRO A1.2.S TITLE: Conduct A Shutdown Safety Assessment and Determine Time to Saturation. PROGRAM APPLICABLE: SOT SOCT____ OLT X LOCT____ ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL 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: Correctly Assess Time to Saturation using TABLE A of UOP-4.0. Complete the Core Cooling section of a Shutdown Safety Assessment using Fig 1A of UOP-4.0. Examinee: Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary) EXAMINER: Developer H. Fitzwater 10/26/09 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP HL T-33 ADMIN Page 1 of 5 A.1.2.S Conduct of Operations ADMIN G2.1.25 - SRO A1.2.S TITLE: Conduct A Shutdown Safety Assessment and Determine Time to Saturation. PROGRAM APPLICABLE: SOT SOCT OL T ---.2L LOCT __ ACCEPTABLE EVALUATION METHOD: ---.2L.. PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 20 MIN SIMULATORICNUMBER: NIA ALTERNATE PATH TIME CRITICAL 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: Correctly Assess Time to Saturation using TABLE A ofUOP-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 0 Evaluator Comments (attach additional sheets if necessary) EXAMINER: ________________ _ H. Fitzwater 10/26109 SEE NUREG 1021 FORM ES-301-3

FNP HLT-33 ADMIN A.1.2.S Page 2 of 5 CONDITIONS When I 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 per FNP-0-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 1 is in a Refueling Outage, and has been shutdown for 120 hours. b. IA SG wide range level is 74%; lB SG wide range level is 75%; 1C SG wide range level is 10%. c. RCS temperature is 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. 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. j. You are directed to determine the time to saturation and prepare the CORE COOLING SECTION ONLY of a shutdown safety assessment on Unit I per FNP-0-UOP-4.0, Appendix 1, step 4.3 and step 4.4. INITIATING CUE: You may begin. EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS: (CIRCLE) START TIME NOTE: Since task may be performed as a group classroom task, elements 1 through 8 may be evaluated by reviewing the completed paperwork.

1. PER STEP 4.3, determine and document at bottom of Figure 1A:

Time to saturation IF core cooling were lost: J hours JL minutes Select Table using given data Select applicable page of table. Select column for given RCS level Select row for time after Shutdown Identify time Identify units for time

1) Written in bottom line of Figure 1A:

(a). 0.0 hours. (b). 9.2 minutes. ° Table A (Full Core) ° Select page 2 of 3 (120°F) ° Select column 2: (MIDLOOP) ° Select row 6 (120 hours) ° Identify 9.2 ° Identify mm from column header S/U NOTE: For Element numbers 2 through 7, the LINE number correlates to the Core Cooling Shutdown Safety Function Evaluation, Figure 1A of Appendix I of FNP-0-UOP-4.0. Elements 2 through 8 are per step 4.4 of the appendix. FNP HL T-33 ADMIN A.1.2.S Page 2 of 5 CONDITIONS When I 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 per FNP-0-UOP-4.0, Appendix 1, step 4.3 and step 4.4. The conditions under which this task is to be performed are:

a.

Unit I is in a Refueling Outage, and has been shutdown for 120 hours.

b.

IA SG wide range level is 74%; IB SG wide range level is 75%; I C SG wide range level is 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.

1.

Another operator is evaluating the other SHUTDOWN SAFETY FUNCTION/CRITERIAS. J. You are directed to determine the time to saturation and prepare the CORE COOLING SECTION ONLY of a shutdown safety assessment on Unit I per FNP-0-UOP-4.0, Appendix 1, step 4.3 and step 4.4. INITIATING CUE: "You may begin." EV ALUA TION CHECKLIST ELEMENTS: START TIME STANDARDS: RESULTS: (CIRCLE) NOTE: Since task may be performed as a group classroom task, elements 1 through 8 may be evaluated by reviewin the com leted a erwork.

I. PER STEP 4.3, determine and document at bottom of Figure lA:

Time to saturation IF core cooling were lost: -.lliL hours JQL minutes Select Table using given data Select applicable page of table. Select column for given RCS level Select row for time after Shutdown Identify time Identify units for time

1) Written in bottom line of Figure IA:

(a). 0.0 hours. (b). 9.2 minutes. ° Table A (Full Core) ° Select page 2 of 3 (120°F) ° Select column 2: (MIDLOOP) ° Select row 6 (120 hours) ° Identify 9.2 ° Identify "min" from column header S I U NOTE: For Element numbers 2 through 7, the "LINE" number correlates to the Core Cooling Shutdown Safety Function Evaluation, Figure IA of Appendix I ofFNP-0-UOP-4.0. Elements 2 through 8 are per step 4.4 of the appendix.

FNPHLT-33ADMIN A.1.2.S Page3of5 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 2. LINE 1:> 2 SGs Avail with loops filled (Ref.

2) Zero (0) written on the line for S /

U step 2.7).- evaluate SG availability: item 1. SG tubes filled and vented; considered filled o Midloop filled and vented and vented if RCS has remained >100 psig and < 100 psig since last fill and vent.

3. LINE 2:Cavity level 152 9

3) Zero (0) written on the line for S / U item 2.

4. LINE 3:RHR subsystems Available (0,1, or 2)

4) Two (2) written on the line for S /

U item 3.

5. LINE 4:RCS level> 126 6

5) Zero (0) written on the line for 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 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 Cooling in? 8. Evaluates Core Cooling condition

8) Circle around ORANGE S /

U condition for the Core Cooling Function OR., if cued per NOTE State the condition is ORANGE 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 HL T-33 ADMIN A.1.2.S Page 3 of 5 EVALUATION CHECKLIST ELEMENTS:

2. LINE 1:22 SGs Avail with loops filled (Ref.

step 2.7).- evaluate SG availability: SG tubes filled and vented; considered filled and vented ifRCS has remained ::::.100 psig since last fill and vent.

3. LINE 2:Cavity level::::. 152' 9"
4. LINE 3:RHR subsystems Available (0,1, or 2)
5. LINE 4:RCS level::::, 126' 6"
6. LINE 5:Time to saturation >30 minutes OR RCS press >325 psig with at least one RCP available for operation and at least one SG available

7. Core Cooling Subtotal STANDARDS:

2) Zero (0) written on the line for item 1.

o Midloop f. filled and vented and < 100 psig

3) Zero (0) written on the line for item 2.

4) Two (2) written on the line for item 3.

5) Zero (0) written on the line for item 4.

6) Zero (0) written on the line for item 5.

7) Two (2) written on line for Core Cooling Subtotal.

RESULTS: (CIRCLE) S / U S / U S / U S / U S / U S / U 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 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 in?"

8. Evaluates Core Cooling condition

8) Circle around ORANGE 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 S / U CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNP HLT-33 ADMIN A.1.2.S Page 4 of 5 GENERAL

REFERENCES:

1. FNP-0-UOP-4.0, VER 36.0

2. KA: G2.1.25 RO 3.9 SRO 4.2 GENERAL TOOLS AND EQUIPMENT:

1. References to be accessed via classroom computer (using exam ID logon) and Exam Reference disklfiles only. 2. Provide copy of FNP-0-UOP-4.0 Table A, Table B, Appendix 1 3. Pen/Pencil 4. Calculator (optional-not required to complete this task) Critical ELEMENT justification: STEP Evaluation 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. Critical - Each line item is critical to evaluate proper assessment of each parameter. The aggregate effect of errors made within each line could result in obtaining the correct end point; therefore each sub-step must be evaluated to ensure examinee is correctly assessing the parameters. 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 FNP HL T-33 ADMIN A.1.2.S Page 4 of 5 GENERAL

REFERENCES:

l. FNP-0-UOP-4.0, VER 36.0

2. KA: G2.1.25 RO 3.9 SRO 4.2 GENERAL TOOLS AND EQUIPMENT:

l. References to be accessed via classroom computer (using exam ID logon) and Exam Reference disk/files only.

2. Provide copy ofFNP-0-UOP-4.0 Table A, Table B, Appendix 1

3. Pen/Pencil

4. Calculator (optional-not required to complete this task)

Critical ELEMENT justification: STEP

l.

2.

3.

4.

5.

6.

7.

8.

COMMENTS: References expected to be utilized:

1. FNP-0-UOP-4.0, ver 36.0

1. 2 SOs Avail with loops filled (Ref step 2.7) 2. Cavity level 1529 3. RHR Subsystems Available (0, 1 or 2) 4. RCS level 126 6 5. Time to saturation > 30 minutes OR RCS press > 325 psig with at least one RCP available for operation and at least one SG available Core Cooling Subtotal 1. 1 A Train DG Available 2. 1 B Train DO Available 3. F 4160 V BUS normal (Aligned to A SUT) 4. G 4160 V BUS normal (Aligned to B SUT) 5. 2 Feeds available to the HV Switchyard (0, 1 or 2) Power Availability Subtotal 0-I RED 42 5 GREEN (GREEN if Defueled) Name Prepared By: App-i, Fig 2 Evaluated LI SHUTDOWN SAFETY FUNCTION! CRITERIA CONDITION (No/FaIseO, Yes/Truel, Use number within range when required) (Circle Condition) REACTIVITY Subtotal Condition AOP 1. No Core Alterations in Progress 0-1 RED 41 2. Number of Boration Flow Paths (0, 1, 2) (Ref step 2.13) 2 ORANGE 41 3. RCS Boron: CSD/Refueling Concentration 34 YELLOW 41 4. Source Range Instrumentation Available 5 GREEN (GREEN if Defueled) Reactivity Subtotal CORE COOLING Subtotal Condition AOP 0 0 2 0 0 2 POWER AVAILABILITY Subtotal Condition Mm required is to CIRCLE the condition ORANGE including the subtotal or the AOP is not required. 0-2 RED 3 ORANGE 4-5 YELLOW 6 GREEN CONTAINMENT Subtotal Condition AOP 1. Refueling Integrity Set 0-I 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 5. RCSlevel126 6 (3 pts) (GREEN if Defueled) Containment Subtotal INVENTORY Subtotal Condition AOP 1. Refueling Cavity 23 Feet (i42i) Above Fuel 0 RED 45 2. LHSI Pump/Flowpath Available I ORANGE 45 3. HHSI Pump/Flowpath Available 2 YELLOW 45 4. RCS is Intact below the Reactor Vessel Flange 3-4 GREEN (GREEN if Defueled) Inventory Subtotal RCS INTEGRITY Subtotal Condition AOP 1. All S/G Manways or Nozzle Dams Installed 0-I ORANGE 46 2. RCS is Intact below the Reactor Vessel Flange 2 YELLOW 46 3. Pressurizer level < 100% GREEN RCS Integrity Subtotal (GREEN if Defueled) SPENT FUEL COOLING Subtotal Condition AOP 1. SFP level 23 feet (1516) above fuel (4 pts) 0-4 RED 47 2. A Tm SFP Cooling available 5 ORANGE 47 3. B Tm SFP Cooling available 6 YELLOW 47 4. 2 SFP Makeup Sources (RWST, DW, RMW to Blender, Boric Acid to GREEN Blender, RHT to transfer canal with weir gate removed) 5FF Subtotal r Time to saturation IF core cooling were lost: 0 hours 9.2 minutes Page 6 of 18 Current Version 1 Header information is not required for this Task; but if requested use current date and time. Prepared By:-,:I=N=am=e===-__ App-!, Fig 2 Evaluated 0 SHUTDOWN SAFETY FUNCTIONI CRITERIA CONDITION (No/False=O, Yes/True=l, Use number within range when required) (Circle Condition) REACTIVITY Subtotal Condition AOP

l.

No Core Alterations in Progress a-I RED 41

2.

Number of Boration Flow Paths (0, 1,2) (Ref step 2.13) 2 ORANGE 41

3.

RCS Boron: CSD/Refueling Concentration 3-4 YELLOW 41

4.

Source Range Instrumentation Available 5 GREEN (GREEN ifDefueled) Reactivity Subtotal CORE COOLING Subtotal Condition AOP

l.

2: 2 SGs Avail with loops filled (Ref step 2.7) 0 0-1 RED 42 0

1t'~1III!.Jl~ !til!! !A1I'f *Y"'!! !1ft" ~EII!! !!Alii! ~., -{IIII!! !!.&"'!! !!1,

2.

Cavity level:2: 152'9" _2_ ~{~'i"J-i*'~I~~,;;JJ,;;JJt~J_'*',",J

3.

RHR Subsystems Available (0, 1 or 2) _0_ ~5 GREEN

4.

RCS level :2: 126' 6" (GREEN if Defueled) Min required is to

5.

Time to saturation> 30 minutes OR RCS press> 325 psig with at least 0 one RCP available for operation and at least one SG available "CIRCLE" the Core Cooling Subtotal 2 condition "ORANGE" POWER AVAILABILITY Subtotal Condition

l.

1 "A" Train DG Available 0-2 RED including the

2.

I "B" Train DG Available 3 ORANGE subtotal or the AOP

3.

F 4160 V BUS normal (Aligned to A SUT) 4-5 YELLOW is not required.

4.

G 4160 V BUS normal (Aligned to B SUT) 6 GREEN

5.

2 Feeds available to the HV Switchyard (0, I or 2) Power Availability Subtotal CONTAINMENT Subtotal Condition AOP

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

4.

Equipment Hatch & Air Locks Closed or Capable of Being Closed on 7 GREEN Short Notice (GREEN ifDefueled)

5.

RCS level :2: 126' 6" (3 pts) Containment Subtotal INVENTORY Subtotal Condition AOP

l.

Refueling Cavity:2: 23 Feet (142'1") Above Fuel a RED 45

2.

LHSI Pump/Flowpath Available 1 ORANGE 45

3.

HHSI Pump/Flowpath Available 2 YELLOW 45

4.

RCS is Intact below the Reactor Vessel Flange 3-4 GREEN (GREEN if Defueled) Inventory Subtotal RCS INTEGRITY Subtotal Condition AOP

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 RCS Integrity Subtotal (GREEN ifDefueled) SPENT FUEL COOLING Subtotal Condition AOP

l.

SFP level :2: 23 feet (151' 6") above fuel (4 pts) 0-4 RED 47

2.

A Trn SFP Cooling available 5 ORANGE 47

3.

B Trn SFP Cooling available 6 YELLOW 47 7 GREEN

4.

2: 2 SFP Makeup Sources (RWST, DW, RMW to Blender, Boric Acid to Blender, RHT to transfer canal with weir gate removed)

SFP Subtotal I I Time to saturation IF core cooling were lost: I ° hours 9.2 minutes i Page 6 of 18 Current Version

FNP HLT-33ADMIN A.1.2S HANDOUT Pg 1 of I CONDITIONS When I 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 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 I is in a Refueling Outage, and has been shutdown for 120 hours. b. 1A SG wide range level is 74%; lB SG wide range level is 75%; 1C SG wide range level is 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. j. You are directed to determine the time to saturation and prepare the CORE COOLING SECTION ONLY of a shutdown safety assessment on Unit 1 per FNP-0-UOP-4.0, Appendix 1, step 4.3 and step 4.4. FNP HL T-33 ADMIN A.1.2S HANDOUT Pg 1 of 1 CONDITIONS When I 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 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 1 is in a Refueling Outage, and has been shutdown for 120 hours.

b. lA SG wide range level is 74%; IB SG wide range level is 75%; lC SG wide range level is 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.

1.

Another operator is evaluating the other SHUTDOWN SAFETY FUNCTION/CRITERIAS.

j. You are directed to determine the time to saturation and prepare the CORE COOLING SECTION ONLY of a shutdown safety assessment on Unit 1 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 TABLE A TABLE A Power-Uprated Unit Time To Saturation: Full Core Assumed Initial Temperature 100°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 Cavity Full (hours) (mm) (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) (ft3) 9591 Page 1 of 3 Version 36.0 11/13/09 12:03:44 TABLE A Power-Up rated Unit Time To Saturation: Full Core FNP-0-UOP-4.0 TABLE A 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 Cavity Full (hours) (min) (min) (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) (ft3) 9591 Page 1 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 = 120°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 Cavity Full (hours) (mm) (mm) (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: 3 ft Below Flange (ft3) 348 Total = 1293 Volume: Full Reactor Cavity (ft3) 39750 Total = 41043 Volume: Full RCS (including Pzr) (ft3) 9591 Page 2 of 3 Version 36.0 11113/09 12:03:44 TABLE A Power-Up rated Unit Time To Saturation: Full Core FNP-0-UOP-4.0 TABLE A Assumed Initial Temperature = 120°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 Cavity Full (hours) (min) (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: 3 ft Below Flange (ft3) 348 Total = 1293 Volume: Full Reactor Cavity (ft3) 39750 Total = 41043 Volume: Full RCS (including pzr) (ft3) 9591 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 3 ft Below Flange Full Reactor RCS Full (hours) (mm) (mm) Cavity (hours) (hours) 0.8 40 4.9 6.7 3.5 0.9 60 5.6 7.6 4.0 1.0 80 6.1 8.3 4.4 1.1 100 6.6 9.1 4.8 1.2 120 7.2 9.8 5.2 1.3 140 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 1.8 336 10.9 14.9 7.9 2.2 504 13.3 18.2 9.6 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: Full RCS (including Pzr) (ft3) 9591 Page 3 of 3 Version 36.0 11/13/09 12:03:44 Time After TABLE A Power-Uprated Unit Time To Saturation: Full Core Assumed Initial Temperature = 140°F Time To Time To Time To Saturation Saturation Saturation FNP-0-UOP-4.0 TABLE A Time To Saturation Shutdown at Midloop 3 ft Below Flange Full Reactor RCS Full (hours) (min) (min) Cavity (hours) (hours) 40 4.9 6.7 3.5 0.8 60 5.6 7.6 4.0 0.9 80 6.1 8.3 4.4 1.0 100 6.6 9.1 4.8 1.1 120 7.2 9.8 5.2 1.2 140 7.6 10.4 5.5 1.3 160 8.1 11.1 5.9 1.4 180 8.5 11.6 6.1 1.4 200 8.9 12.1 6.4 1.5 336 10.9 14.9 7.9 1.8 504 13.3 18.2 9.6 2.2 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: Full RCS (includingpzr) (ft3) 9591 Page 3 of3 Version 36.0

11/13/09 12:03:44 TABLE B Power-Uprated Unit FNP-0-UOP-4.0 TABLE B Time To Saturation: One-Third New Fuel Assumed Initial Temperature = 100°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) (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): 945 Volume: 3 ft Below Flange (ft3) 348 Total = 1293 Volume: Full Reactor Cavity (ft3) 39750 Total = 41043 Volume: Full RCS (including Pzr) (ft3) 9591 Page 1 of3 Version 36.0 11113/09 12:03:44 Time After TABLEB Power-Up rated Unit Time To Saturation: One-Third New Fuel Assumed Initial Temperature = lOO°F Time To Time To Time To Saturation Saturation Saturation FNP-0-UOP-4.0 TABLEB Time To Saturation RCS Shutdown at Midloop 3 ft Below Flange Full Reactor Full (hours) (min) (min) 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): 945 Volume: 3 ft Below Flange (ft3) 348 Total = 1293 Volume: Full Reactor Cavity (ft3) 39750 Total = 41043 Volume: Full RCS (including pzr) (ft3) 9591 Page 1 of3 Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 TABLE B TABLE B Power-Uprated 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 3 ft Below Flange Full Reactor Full (hours) (mm) (mm) 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: 3 ft Below Flange (ft3) 348 Total = 1293 Volume: Full Reactor Cavity (ft3) 39750 Total = 41043 Volume: Full RCS (including Pzr) (ft3) 9591 Page 2 of 3 Version 36.0 11113/09 12:03:44 Time After TABLEB Power-Up rated Unit Time To Saturation: One-Third New Fuel Assumed Initial Temperature = 120°F Time To . Time To Time To Saturation Saturation Saturation FNP-0-UOP-4.0 TABLEB Time To Saturation RCS Shutdown at Midloop 3 ft Below Flange Full Reactor Full (hours) (min) (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: 3 ft Below Flange (ft3) 348 Total = 1293 Volume: Full Reactor Cavity (ft3) 39750 Total = 41043 Volume: Full RCS (including pzr) (ft3) 9591 Page 2 of3 Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 TABLE B TABLE 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 3 ft Below Flange Full Reactor Full (hours) (mm) (mm) 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: 3 ft Below Flange (ft3) 348 Total = 1293 Volume: Full Reactor Cavity (ft3) 39750 Total = 41043 Volume: Full RCS (including Pzr) (ft3) 9591 Page 3 of 3 Version 36.0 11/13/09 12:03:44 Time After TABLEB Power-Uprated Unit Time To Saturation: One-Third New Fuel Assumed Initial Temperature = 140°F Time To Time To Time To Saturation Saturation Saturation FNP-0-UOP-4.0 TABLEB Time To Saturation RCS Shutdown at Midloop 3 ft Below Flange Full Reactor Full (hours) (min) (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: 3 ft Below Flange (ft3) 348 Total = 1293 Volume: Full Reactor Cavity (ft3) 39750 Total = 41043 Volume: Full RCS (including pzr) (ft3) 9591 Page 3 of3 Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 FARLEY NUCLEAR PLANT SHARED UISTIT OPERATING PROCEDURE UOP-4.0 APPENDIX 1 1.0 Purpose The purpose of the Shutdown Safety Assessment is to provide a means for evaluating the safety condition of the plant when in Modes 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 Yellow Condition - The plants ability to perform the associated safety function is reduced but is at an acceptable level. 2.3 Orange Condition - The plants 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 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> 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 1 of 18 Version 36.0 11113/09 12:03:44 1.0 Purpose F ARLEY NUCLEAR PLANT SHARED UNIT OPERATING PROCEDURE UOP-4.0 APPENDIX 1 FNP-0-UOP-4.0 APPENDIX 1 The purpose ofthe Shutdown Safety Assessment is to provide a means for evaluating the safety condition of the plant when in Modes 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 Yellow Condition - The plant's ability to perform the associated safety function is reduced but is at an acceptable level. 2.3 Orange Condition - The 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 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:::: 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 1 of 18 Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 2.9 One DIG Available - The selected DIG is capable of being started (either manually or automatically) and supplying 4160 V power to its respective 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 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 /Flow Path Available - A RHR 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. 2.13 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 OR FNP-2-STP-2.1 , BORON INJECTION FLOW PATH VERIFICATION AND BORIC ACID TRANSFER PUMP OPERABILITY TEST, MODES 5 & 6 AND by a current FNP-1-STP-3.2 OR FNP-2-STP-3.2, BORATED WATER SOURCE OPERABILITY TEST MODE 5,6. Additionally, Normal charging can be considered an available boration flow path under the following conditions: 2.13.1 Q1E21MOV81O7 and Q1E21MOV81O8 are open, OR Q2E21MOV81O7 and Q2E21M0V8108 are open. 2.13.2 With one of the following charging pump requirements met. 1A or 2A Charging Pump available lB Charging Pump Available with Q1E21MOV8132A and B open, OR 2B Charging Pump Available with Q2E21M0V8132A and B open 1C Charging pump available with Q1E21MOV8132A and B open, OR 2C Charging pump available with Q2E21MOV8132A and B open Page 2 of 18 Version 36.0 11113/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 2.9 One DIG Available - The selected DIG is capable of being started (either manually or automatically) and supplying 4160 V power to its respective 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. (AI 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 I Flow Path Available - A RHR pump is capable of injecting water into the RCS from the 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-I-STP-2.1 OR FNP-2-STP-2.1,BORON INJECTION FLOW PATH VERlFICA nON AND BORlC ACID TRANSFER PUMP OPERABILITY TEST, MODES 5 & 6 AND by a current FNP-1-STP-3.2 OR FNP-2-STP-3.2, BORA TED WATER SOURCE OPERABILITY TEST MODE 5, 6. Additionally, Normal charging can be considered an available boration flow path under the following conditions: 2.13.1 QIE21MOV8107 and Q1E21MOV8108 are open, OR Q2E21MOV8107 and Q2E21MOV8108 are open. 2.13.2 With one of the following charging pump requirements met. lA or 2A Charging Pump available 1B Charging Pump Available with Q1E21MOV8132A and B open, OR 2B Charging Pump Available with Q2E21MOV8132A and B open lC Charging pump available with QIE21MOV8132A and B open, OR 2C Charging pump available with Q2E21MOV8132A and B open Page 2 of 18 Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 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 current position is that the plant will not be intentionally placed in this condition. Review FNPs commitment to NUMARC 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.
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 3.0 Precautions and Limitations FNP-0-UOP-4.0 APPENDIX 1 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. FNP's current position is that the plant will not be intentionally placed in this condition. Review FNP's commitment to NUMARC 91-06. 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.
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

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 4.3 IF in mode 5 or 6, THEN determine the time to saturation for existing plant conditions using the IPC (preferred) or FNP-0-UOP-4.0 Table A or B. Enter time on Figure 1A of Appendix 1. 4.4 Evaluate the criteria listed below each Shutdown Safety Function as follows. NOTE: Refer to Definitions to assist in the evaluation as appropriate. 4.4.1 IF the reactor is defueled, THEN 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 1 in its blank or use the number/range of numbers listed in (). 4.4.3 IF the criteria is NOT met, THEN place a 0 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 1A or lB to indicate the review of the Figure 2 posting requirements {AI 2001203573). 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 1 have been performed for the affected Shutdown Safety Functions. Page 4 of 18 Version 36.0 11113/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 4.3 IF in mode 5 or 6, THEN determine the time to saturation for existing plant conditions using the IPC (preferred) or FNP-0-UOP-4.0 Table A or B. Enter time on Figure lA of Appendix 1. 4.4 Evaluate the criteria listed below each Shutdown Safety Function as follows. NOTE: Refer to Definitions to assist in the evaluation as appropriate. 4.4.1 IF the reactor is defueled, THEN 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 1 in its blank or use the number/range of numbers listed in ( ). 4.4.3 IF the criteria is NOT met, THEN place a 0 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 or IB to indicate the review of the Figure 2 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 1 have been performed for the affected Shutdown Safety Functions. Page 4 of 18 Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 4.8 Evaluate the activities planned for the next 12 hours to determine if the plant may 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 current position is that the plant will not be intentionally placed in this condition. Review FNPs commitment to NUMARC 9 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 9 1-06, Guidelines For Industry Actions To Assess Shutdown Management. 4.2 10CFR5O.65 (a)(4) 4.3 NUMARC 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 11/13/09 12:03 :44 FNP-0-UOP-4.0 APPENDIX 1 4.8 Evaluate the activities planned for the next 12 hours to determine if the plant may 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. FNP's current position is that the plant will not be intentionally placed in this condition. Review FNP's commitment to NUMARC 91-06. 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, Guidelines For Industry Actions To Assess Shutdown Management. 4.2 10CFR50.65 (a)(4) 4.3 NUMARC 93-01, 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

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 Figure IA SHUTDOWN SAFETY ASSESSMENT (Modes 5, 6 and Defueled) Unit:_ Prepared By:__________________ Date: Time:______ App-i, Fig 2 Evaluated LI SHUTDOWN SAFETY FUNCTION! CRITERIA CONDITION (NoIFalseO, Yes/True=1, Use number within range when required) (Circle Condition) REACTIVITY Subtotal Condition AOP I. No Core Alterations in Progress 0-1 RED 41 2. Number of Boration Flow Paths (0, 1, 2) (Ref step 2.13) 2 ORANGE 41 3. RCS Boron: CSD/Refueling Concentration 3-4 YELLOW 41 4. Source Range Instrumentation Available 5 GREEN (GREEN if Defueled) Reactivity Subtotal CORE COOLING Subtotal Condition AOP 1. 2 SOs Avail with loops filled (Ref step 2.7) 01 RED 42 2. Cavity level 1529 2-3 ORANGE 42 3. RHR Subsystems Available (0, 1 or 2) 4 YELLOW 42 5 GREEN 4. RCS level 126 6 (GREEN if Defueled) 5. Time to saturation > 30 minutes OR RCS press > 325 psig with at least one RCP available for operation and at least one SG available Core Cooling Subtotal POWER AVAILABILITY Subtotal Condition AOP 1. 1 A Train DG Available 0-2 RED 43 2. 1 B Train DO Available 3 ORANGE 43 3. F 4160 V BUS normal (Aligned to A SUT) 45 YELLOW 43 4. G 4160 V BUS normal (Aligned to B SUT) 6 GREEN 5. 2 Feeds available to the HV Switchyard (0, 1 or 2) Power Availability Subtotal CONTAINMENT Subtotal Condition AOP 1. 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 4. Equipment Hatch & Air Locks Closed or Capable of Being Closed on 7 GREEN Short Notice (GREEN if Defueled) 5. RCS level 126 6 (3 pts) Containment Subtotal INVENTORY Subtotal Condition AOP 1. RefuelingCavity23 Feet(142l)AboveFuel 0 RED 45 2. LHSI Pump/Flowpath Available I ORANGE 45 3. HHSI Pump/Flowpath Available 2 YELLOW 45 4. RCS is Intact below the Reactor Vessel Flange 3-4 GREEN (GREEN if Defueled) Inventory Subtotal RCS INTEGRITY Subtotal Condition AOP 1. 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 RCS Integrity Subtotal (GREEN if Defueled) SPENT FUEL COOLING Subtotal Condition AOP 1. SFP level 23 feet (1516) above fuel (4 pts) 0-4 RED 47 2. A Tm SFP Cooling available 5 ORANGE 47 3. B Tm SFP Cooling available 6 YELLOW 47 4. 2 SFP Makeup Sources (RWST, DW, RMW to Blender, Boric Acid to 7 GREEN Blender, RHT to transfer canal with weir gate removed) SFP Subtotal Time to saturation JE core cooling were lost: hours minutes Page 6 of 18 Version 36.0 11113/09 12:03:44 Figure IA FNP-0-UOP-4.0 APPENDIX 1 SHUTDOWN SAFETY ASSESSMENT (Modes 5, 6 and Defueled) Unit:_ Prepared By: ________ Date: ____ Time:___ App-l, Fig 2 Evaluated 0 II SHUTDOWN SAFETY FUNCTION/ CRITERIA CONDITION 'ilUI;;' 1, Use number with' n required) (Circle Condition) REACTIVITY Subtotal Condition AOP

l.

No Core Alterations in Progress 0-1 RED 41

2.

Number of Boration Flow Paths (0, 1,2) (Ref step 2.l3) 2 ORANGE 41

3.

RCS Boron: CSD/Refueling Concentration 3-4 YELLOW 41

4.

Source Range Instrumentation Available 5 GREEN Reactivity Subtotal (GREEN ifDefueled) CORE COOLING Subtotal Condition AOP

l.

2 SGs Avail with loops filled (Ref step 2.7) 0-1 RED 42

2.

Cavity level;;:: 152 '9" 2-3 ORANGE 42

3.

RHR Subsystems Available (0, 1 or 2) 4 YELLOW 42

4.

RCS level;;:: 126' 6"

5 GREEN

5.

Time to saturation> 30 minutes OR RCS press> 325 psig with at least (GREEN ifDefueled) one RCP available for operation and at least one SG available Core Cooling Subtotal POWER A V AILABILITY Subtotal Condition AOP

l.

1 "A" Train DG Available 0-2 RED 43

2.

1 "B" Train DG Available 3 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, 1 or 2) Power Availability Subtotal CONTAINMENT Subtotal Condition AOP

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

4.

Equipment Hatch & Air Locks Closed or Capable of Being Closed on 7 GREEN Short Notice (GREEN ifDefueled)

5.

RCS level;;:: 126' 6" (3 pts) Containment Subtotal INVENTORY Subtotal Condition AOP

l.

Refueling Cavity;;:: 23 Feet (142' I") Above Fuel 0 RED 45

2.

LHSI Pump/Flowpath Available I ORANGE 45

3.

HHSI Pump/Flowpath Available 2 YELLOW 45

4.

RCS is Intact below the Reactor Vessel Flange 3-4 GREEN (GREEN ifDefueled) InventOl'y Subtotal RCS INTEGRITY Subtotal Condition AOP

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 RCS Integrity Subtotal (GREEN ifDefueled) SPENT FUEL COOLING Subtotal Condition AOP

l.

SFP level;;:: 23 feet (151 '6") above fuel (4 pts) 0-4 RED 47

2.

A Trn SFP Cooling available 5 ORANGE 47

3.

B Trn SFP Cooling available 6 YELLOW 47

4.

2 SFP Makeup Sources (RWST, DW, RMW to Blender, Boric Acid to 7

GREEN Blender, RHT to transfer canal with weir gate removed) SFP Subtotal Time to saturation IF core cooling were lost: hours minutes Page 6 of 18 Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 FIGURE lB SHUTDOWN SAFETY ASSESSMENT (Mode 4) Unit: Prepared By:_______________ Date: Time:______ App-i, Fig 2 Evaluated LI SHUTDOWN SAFETY FUNCTION! CRITERIA CONDITION (Circle Condition) (No!False0, Yes/Truel, Use number within range when required) REACTIVITY Subtotal Condition AOP 1. No positive reactivity changes in Progress 0-1 RED 41 2. Number of Boration Flow Paths (0, 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 5 GREEN Reactivity Subtotal CORE COOLING Subtotal Condition AOP 1. 2 SGs Available (2 pts if 2 S/Gs Available (Ref step 2.7) 0-1 RED 42 2. RHR Subsystems Available (0, 1 or 2) 2-3 ORANGE 42 3. PRZ level within normal operating band 4 YELLOW 42 4. RCS Subcooling Margin > 16° F GREEN Core Cooling Subtotal POWER AVAILABILITY Subtotal Condition AOP 1. 1 A Train DG Available 0-2 RED 43 2. 1 B Train DG Available 3 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, 1 or 2) Power Availability Subtotal CONTAINMENT Subtotal Condition AOP 1. 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. PRZ level within normal operating band 0 RED 45 2. LHSI Pump!Flowpath Available 1 ORANGE 45 3. HHSI Pump!Flowpath Available 2 YELLOW 45 4. Normal make-up capability available 3-4 GREEN Inventory Subtotal RCS INTEGRITY Subtotal Condition AOP 1. LTOP TECH SPEC MET 0-1 ORANGE 46 2. RCS!PRZ cooldown rate < tech spec allowable 2 YELLOW 46 3. Pressurizer operable per tech specs 3 GREEN RCS Integrity Subtotal SPENT FUEL COOLING Subtotal Condition 1. SFP level 23 feet (1516) above fuel (4 pts) 0-4 RED 47 2. A Tm SFP Cooling 5 ORANGE 47 3. B Tm SFP Cooling 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 FIGURE IB SHUTDOWN SAFETY ASSESSMENT (Mode 4) FNP-0-UOP-4.0 APPENDIX 1 Unit: __ Prepared By: _______ Date: ____ Time:___ App-l, Fig 2 Evaluated 0 SHUTDOWN SAFETY FUNCTIONI CRITERIA CONDITION (Circle Condition) (NolFalse=O, Yes/True= 1 Use number within range when required) REACTIVITY Subtotal Condition AOP

l.

No positive reactivity changes in Progress 0-1 RED 41

2.

Number of Boration Flow Paths (0, 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 5 GREEN Reactivity Subtotal CORE COOLING Subtotal Condition AOP

l.

2 SGs Available (2 pts if~ 2 S/G's Available (Ref step 2.7) 0-1 RED 42

2.

RHR Subsystems Available (0, 1 or 2) 2-3 ORANGE 42

3.

PRZ level within normal operating band 4 YELLOW 42

4.

RCS Subcooling Margin> 16° F ~5 GREEN Core Cooling Subtotal POWER A V AILABILITY Subtotal Condition AOP

l.

1 "A" Train DG Available 0-2 RED 43

2.

1 "B" Train DG Available 3 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, 1 or 2) Power Availability Subtotal CONTAINMENT Subtotal Condition AOP

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

l.

PRZ level within normal operating band 0 RED 45

2.

LHSI Pump/Flowpath Available I ORANGE 45

3.

HHSI Pump/Flowpath Available 2 YELLOW 45

4.

Normal make-up capability available 3-4 GREEN Inventory Subtotal RCS INTEGRITY Subtotal Condition AOP

l.

L TOP TECH SPEC MET 0-1 ORANGE 46

2.

RCS/PRZ cooldown rate < tech spec allowable 2 YELLOW 46

3.

Pressurizer operable per tech specs 3 GREEN RCS Integrity Subtotal SPENT FUEL COOLING Subtotal Condition

l.

SFP level ~ 23 feet (151 '6") above fuel (4 pts) 0-4 RED 47

2.

A Trn SFP Cooling 5 ORANGE 47

3.

B Trn SFP Cooling 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

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 Figure 2 Yellow/Orange Condition Signs Required for Single Train Availability IF required by step 4.6, THEN place caution signs at applicable location specified in Table 2 for Unit 1 or Table 3 for Unit 2. 2. Signs should be worded similar to the following: TRAIN OUTAGE IN PROGRESS NO WORK IS TO BE DONE ON THE CALL EXT. 3. Complete Table 2 or 3 to document the review of posting requirements. 3.1 Mark as N/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 8 of 18 Version 36.0 11113/09 12:03:44 Figure 2 FNP-0-UOP-4.0 APPENDIX 1 Yellow/Orange Condition Signs Required for Single Train Availability

1.

IF required by step 4.6, THEN place caution signs at applicable location specified in Table 2 for Unit 1 or Table 3 for Unit 2.

2.

Signs should be worded similar to the following: TRAIN OUT AG E IN PROGRESS NO WORK IS TO BE DONE ON THE TRAIN C.ALL EXT.

3.

Complete Table 2 or 3 to document the review of posting requirements. 3.1 Mark as N/ 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 Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 TABLE I Contingency Actions Required for Voluntary Entry to a Shutdown Safety Assessment Orange or Yellow condition. Reactivity Orange Condition Contingency Actions for Entry 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 11113/09 12:03:44 TABLE 1 FNP-0-UOP-4.0 APPENDIX 1 Contingency Actions Required for Voluntary Entry to a Shutdown Safety Assessment Orange or Yellow condition. Reactivity Orange Condition Contingency Actions for Entry

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 FNP-0-UOP-4.0 APPENDIX 1 TABLE 1 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 conditions with time to saturation 30 mm., an orange condition may be encountered. 1. IF Orange condition entry is being made as part of Mid Loop Operations, THEN ensure the requirements of FNP-1-UOP-4.3 OR FNP-2-UOP-4.3, MID LOOP OPERATIONS, have been met, including the Mid-Loop Compensatory measures in Appendix 3 of FNP-1-UOP-4.1 OR FNP-2-UOP-4.1, CONTROLLING PROCEDURE FOR 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 Appendix 3 of FNP-1-UOP-4.1 OR FNP-2-UOP-4.1, CONTROLLING PROCEDURE 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 feet (142l) above the fuel. Page 10 of 18 Version 36.0 11113/09 12:03:44 TABLE 1 FNP-0-UOP-4.0 APPENDIX 1 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 conditions with time to saturation::;; 30 min., an orange condition may be encountered.

1.

IF Orange condition entry is being made as part of Mid Loop Operations, THEN ensure the requirements ofFNP-I-UOP-4.3 OR FNP-2-UOP-4.3, MID LOOP OPERATIONS, have been met, including the Mid-Loop Compensatory measures in Appendix 3 of FNP-I-UOP-4.l OR FNP-2-UOP-4.l, CONTROLLING PROCEDURE FOR 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 Appendix 3 ofFNP-I-UOP-4.1 OR FNP-2-UOP-4.1, CONTROLLING PROCEDURE 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 feet (142' 1") above the fuel. Page 10 of18 Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 TABLE 1 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. 2. Refer to Technical Specification 3.8.2. 3. Based on the unit outage, as a minimum, ensure the Unit 1 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 BATP 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 TABLE 1 FNP-0-UOP-4.0 APPENDIX 1 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.

2.

Refer to Technical Specification 3.8.2.

3.

Based on the unit outage, as a minimum, ensure the Unit 1 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 BA 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

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 TABLE 1 Contingency Actions Required for Voluntary Entry to a Shutdown Safety Assessment Orange or Yellow condition. Power Availability Yellow Condition Contingency Actions For Entry 1. Verify RCS level 126 6 prior to voluntary Yellow condition entry. 2. Refer to Technical Specification 3.8.2. 3. Based on the unit outage, as a minimum, ensure the Unit 1 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 BATP 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. Page 12 of 18 Version 36.0 11113/09 12:03:44 TABLE 1 FNP-0-UOP-4.0 APPENDIX 1 Contingency Actions Required for Voluntary Entry to a Shutdown Safety Assessment Orange or Yellow condition. Power Availability Yellow Condition Contingency Actions For Entry

1.

Verify RCS level ~ 126' 6" prior to voluntary Yellow condition entry.

2.

Refer to Technical Specification 3.8.2.

3.

Based on the unit outage, as a minimum, ensure the Unit 1 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 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.

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. Page 120f18 Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 TABLE 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 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 TABLE 1 FNP-0-UOP-4.0 APPENDIX 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 ofFNP-I-UOP-4.3 OR FNP-2-UOP-4.3, MID 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 FNP-0-UOP-4.0 APPENDIX 1 TABLE 1 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 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 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 of 18 Version 36.0 11/13/09 12:03:44 TABLE 1 FNP-0-UOP-4.0 APPENDIX 1 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 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 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 of 18 Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 TABLE 1 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 requirements of FNP-1-UOP-4.3 OR FNP-2-UOP-4.3, MID LOOP OPERATIONS, have been met. 2. WHEN 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 of FNP-1-UOP-4.3 OR FNP-2-UOP-4.3, MID LOOP OPERATIONS, have been met. 2. WHEN 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 11113/09 12:03:44 TABLE 1 FNP-0-UOP-4.0 APPENDIX 1 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 requirements ofFNP-I-UOP-4.3 OR FNP-2-UOP-4.3, MID LOOP OPERATIONS, have been met.

2.

WHEN SO 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 OR FNP-2-UOP-4.3, MID LOOP OPERATIONS, have been met.

2.

WHEN SO 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 FNP-0-UOP-4.0 APPENDIX 1 TABLE 1 Contingency Actions Required for Voluntary Entry to a Shutdown Safety Assessment Orange or Yellow condition. 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 TABLE 1 FNP-0-UOP-4.0 APPENDIX 1 Contingency Actions Required for Voluntary Entry to a Shutdown Safety Assessment Orange or Yellow condition. 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 FNP-0-UOP-4.0 APPENDIX 1 TABLE 2 Protected Train Postings Unit 1 Components Sign Posted Sign Removed Initials Initials Charging Pump 1A (B,C) RHR Pump 1A (B) CCW Pump 1A (B,C) BATP 1A (B) Diesel Generator 1-2A (1C, 2C, IB, 2B) SFP Cooling 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 1A (B, C, D, E) SW Valve Boxes Start Up Transformers 1A, or lB Other Page 17 of 18 Version 36.0 11113/09 12:03:44 TABLE 2 Protected Train Postings Unit 1 Components Sign Posted Initials Charging Pump lA (B,C) RHR Pump lA (B) CCW Pump lA (B,C) BATP lA (B) Diesel Generator 1-2A (lC, 2C, IB, 2B) SFP Cooling lA 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 (B, C, D, E) SW Valve Boxes Start Up Transformers lA, or IB Other Page 17 of 18 FNP-0-UOP-4.0 APPENDIX 1 Sign Removed Initials Version 36.0

11/13/09 12:03:44 FNP-0-UOP-4.0 APPENDIX 1 TABLE 3 Protected Train Postings Unit 2 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 (1C, 2C, or 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, C, D, E) SW Valve Boxes Start Up Transformers 2A or 2B Other Page 18 of 18 Version 36.0 11113/09 12:03:44 TABLE 3 Protected Train Po stings Unit 2 Components Sign Posted 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 ) 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, C, D, E) SW Valve Boxes Start Up Transformers 2A or 2B Other Page 18 of 18 FNP-0-UOP-4.0 APPENDIX 1 Sign Removed Initials Version 36.0

FNP HLT-33 ADMIN Page 1 of 7 A.2.1.A Equipment Control ADMIN 001A4.11-RO & SRO A.2.1.A TITLE: Perform A Shutdown Margin Calculation in modes 1 & 2. PROGRAM APPLICABLE: SOT SOCT____ OLT X LOCT____ ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL 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 the acceptable ranges identified within each critical elements standard. Identify the need to emergency borate. Examinee: Overall 1PM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary) EXAMINER: Developer H. Fitzwater 10/28/09 NRC Approval SEE NUREG 1021 FORM ES-3013 FNP HL T-33 ADMIN Page 1 of 7 A.2.1.A Equipment Control ADMIN -OOlA4.11-RO & SRO A.2.1.A TITLE: Perform A Shutdown Margin Calculation in modes 1 & 2. PROGRAM APPLICABLE: SOT SOCT OLT ~ LOCT __ ACCEPTABLE EVALUATION METHOD: ~ PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM --.2L CLASSROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: NIA ALTERNATE PATH TIME CRITICAL 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 the acceptable ranges identified within each critical element's standard. Identify the need to emergency borate. Examinee: Overall JPM Performance: Satisfactory 0 V nsatisfactory 0 Evaluator Comments (attach additional sheets if necessary) EXAMINER: ________________ _ H. Fitzwater 10/28/09 SEE NUREG 1021 FORM ES-301-3

FNP HLT-33 ADMIN 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 1 AND 2 (TAVG 547°F), for Unit 1. The conditions under which this task is to be performed are: a. Unit 1 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, 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. Core burnup is 9,800 MWD/MTU burnup. h. FNP-1-STP-29.5, SHUTDOWN MARGIN CALCULATION IN MODES 1 AND 2 (TAVG? 547°F), initial conditions are satisfied. i. The Shift Supervisor has directed you to complete FNP-1-STP-29.5 starting at step 5.1 and identify whether or not emergency boration is required. INITIATING CUE: You may begin. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME NOTE: Elements 1 through 13 are evaluated by comparing the completed Calculation page to the values and ranges of each element. The acceptable responses are ALSO listed on the calculation KEY. 1. Step A.1: Document Core Burnup

1) Value entered: 9,800 MWD S I U

2. Step A.2: Document Power Level

2) Value entered: 90 % entered S I U FNP HL T-33 ADMIN 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 1 AND 2 (TA VG 2: 547°F), for Unit 1. The conditions under which this task is to be performed are:

a. Unit 1 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, 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. Core burnup is 9,800 MWDIMTU burnup.

h. FNP-I-STP-29.5, SHUTDOWN MARGIN CALCULATION IN MODES 1 AND 2 (TAVG2:

547°F), initial conditions are satisfied.

1.

The Shift Supervisor has directed you to complete FNP-I-STP-29.5 starting at step 5.1 and identify whether or not emergency boration is required. INITIATING CUE: "You may begin." EV ALUA TION CHECKLIST ELEMENTS: START TIME STANDARDS: RESULTS: (CIRCLE) NOTE: Elements 1 through l3 are evaluated by comparing the completed Calculation page to the values and ran es of each element. The acce table res onses are ALSO listed on the calculation KEY.

1. Step A.1: Document Core Burnup

1) Value entered: 9,800 MWD S / U

2. Step A.2: Document Power Level

2) Value entered: 90 % entered S / U

FNP HLT-33 ADMIN 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 / U below RIL. (RNG: NONE) a) Using COLR figure 1 determines RIL (a). Determines RIL from COLR for 90% power level. CB D/ RIL 167 (165-170) from COLR. CBC/RJL=FULL OUT (or 229). b) Gathers data from Conditions page (b).Documents given Demand positions CB 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

for RODS below RIL (RNG: 3-8) a) Determines stuck rod in CBD, Determines CBD ML. (a). Determines RIL from COLR P8CBDIRIL=167 (Range: 165-170) from b) Documents given Data for rod P-8 COLR. (b). Documents given data I. Rod#-)P8@162 c) Calculates difference (c). Calculates difference (ML DRPI) 5 (RNG: 3-8) 5. Step B.1: Determine Rod Worth for all

5) Value entered: 6268 pcm.

S / U control and shutdown bands at Zero steps (range: NONE) using given power and burnup: a) Uses Curve 77 pg 1 for 90% power and I0000MWD 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 /

U rods (range: 30-80) FNP HLT-33 ADMIN EVALUATION CHECKLIST ELEMENTS: A.2.1.A

3. Step A.3: Determine penalty steps for Banks below RIL.

a) Using COLR figure 1 determines RIL for 90% power level. b) Gathers data from Conditions page c) Determines penalty steps per bank.

4. Step A.4: Determine number of penalty steps for RODS below RIL a) Determines stuck rod in CBD, Determines CBD RIL.

b) Documents given Data for rod P-8 c) Calculates difference

5. Step B.l: Determine Rod Worth for all control and shutdown bands at Zero steps using given power and burnup:

a) Uses Curve 77 pg 1 for 90% power and 10000MWD Page 3 of 7 STANDARDS:

3) Value entered: ZERO (0)

(RNG: NONE) (a). Determines RIL from COLR CB DI RIL = 167 (165-170) from COLR. CBC I RIL = FULL OUT (or 229). (b). Documents given Demand positions CB DI Demand 192. All others: Full out (or 229) (c). Calculates difference All values: 0 (RNG: NONE) RESULTS: (CIRCLE) S I U

4) Value entered: 5 S I U (RNG: 3-8)

(a). Determines RIL from COLR P8 -7 CB DI RIL = 167 (Range: 165-170) from COLR. (b). Documents given data

i. Rod # -7 P8 @ 162 (c). Calculates difference (RIL - DRPI) = 5 (RNG: 3-8)

5) Value entered: 6268 pcm.

(range: NONE) S I U

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 rods (range: 30-80)

FNP HLT-33 ADMIN A.2.1.A Page 4 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 8. Step B.4.a; Determine most reactive Rod

8) Value entered of 1406 pcm S /

U worth (range: NONE) (a). From Curve 77 pg 2 for < 1 0000MWD. 9. Step B.4.b; Calculate rod worth of 9) Value entered of 3515 5 I U stuck/untrippable rod (RNG: 3515-3516) (a).

of stuck: 1 rod (b).

B.4.a: 1406. (+1 / -0) value for various rounding technique effects)

10. Step B.5; Calculate penalized rod worth

10) Value entered of:

S / U (-) 2432.7 NOTE: NEG (-) SIGN IS IMPORTANT FOR THIS CALCULATION/Evaluation (RNG: (-)2403 to (-) 2451) Transpose data from other steps: (a). B.1: 6268 (b). B.2: 0 (c). B.3: 50 (d). B.4.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 < 1 0000MWD. FNP HL T-33 ADMIN A.2.1.A EV ALUA nON CHECKLIST ELEMENTS:

8. Step B.4.a; Determine most reactive Rod worth
9. Step B.4.b; Calculate rod worth of stuck/untrippable rod
10. Step B.5; Calculate penalized rod worth
11. Step B.6; Determine power defect for given conditions Page 4 of 7 STANDARDS:

RESULTS: (CIRCLE)

8) Value entered of 1406 pcm S / U (range: NONE)

(a). From Curve 77 pg 2 for.:S 10000MWD.

9)

Value entered of3515 S / U (RNG: 3515-3516) (a). # of stuck: 1 rod (b). BA.a: 1406. (+ 1 / -0) value for various rounding technique effects)

10) Value entered of:

(-) 2432.7 NOTE: NEG (-) SIGN IS IMPORTANT FOR THIS CALCULATIONlEvaiuation (RNG: (-)2403 to (-) 2451 ) Transpose data from other steps: (a). B.l: 6268 (b). B.2: 0 (c). B.3: 50 (d). BA.b 3515. Calculate using equation.

11) Value entered of:

1634 pcm (RNG: NONE) (a). From Curve 78 for.:S 10000MWD. S / U S / U

FNP HLT-33 ADMIN A.2.1.A Page 5 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE)

12. Step B.8; Calculate available Shutdown 12)

Value entered of: S / U Reactivity (-) 748.7 (RNG: -718 to -767) NOTE: NEG (-) SIGNIS IMPORTANT FOR THIS CALCULATION/Evaluation (a). Transpose data:

i. B.5: (-) 2432.7 ii. B.6: 1634 iii. Calculate

13. Step B.9; Calculate Excess Shutdown Margin 13)

Value entered of: S / U (+) 1021.3 (RNG: 1003 to 1051) NOTE: POS (+) SIGN IS IMPORTANT FOR THIS 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.

14. Step B.10: Identifies Need to Emergency

14) Notifies Shift Supervisor of S /

U 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 step 5.1 of procedure. c) Asks for verification of calculation 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 HL T-33 ADMIN A.2.1.A EV ALUA nON CHECKLIST ELEMENTS:

12. Step B.8; Calculate available Shutdown Reactivity STANDARDS:

12) Value entered of:

(-) 748.7 (RNG: -718 to -767) NOTE: NEG (-) SIGN IS IMPORTANT FOR THIS CALCULATIONlEva/uation (a). Transpose data:

i. B.5: (-) 2432.7 ii. B.6: 1634 iii. Calculate Page 5 of 7 RESULTS:

(CIRCLE) S / U

13. Step B.9; Calculate Excess Shutdown Margin

13) Value entered of:

S / U (+) 1021.3 (RNG: 1003 to 1051) NOTE: POS (+) SIGN IS IMPORTANT FOR THIS CALCULATIONlEva/uation (a). Transpose data:

i. B.8: (-) 748.7 ii. Calculate Element 15 is not required to be completed but is likely to be completed/initialed if initiated as a rou /classroom settin.

14. Step B.10: Identifies Need to Emergency Borate

15. completes task:

a) Signs and dates Calculation Sheet b) Initials step 5.1 c) Asks for verification of calculation

14) Notifies Shift Supervisor of S / U need to Emergency Borate.

15) Completes sign off.

S / U (a). Signs and dates form (b ).Initials step 5.1 of procedure. 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 ADMIN A.2.1.A Page 6 of 7 GENERAL

REFERENCES:

1. FNP-1-STP-29.5, VER4.0 2.KA:001A4.11 RO 3.5 SRO 4.1 GENERAL TOOLS AND EQUIPMENT:

1. FNP-1-STP-29.5, ver 4.0 2. PCB-VOL1-CRV77, Cycle 23 rev 8 3. PCB-VOL1-CRV78, Cycle 23 rev 8 4. Unit 1, COLR for FNP Uniti Cycle 23, Rev 0 Figure 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: FNP HL T-33 ADMIN A.2.1.A Page 6 of 7 GENERAL

REFERENCES:

1. FNP-l-STP-29.5, VER 4.0

2. KA: 001A4.11 RO 3.5 SRO 4.1 GENERAL TOOLS AND EQUIPMENT:

1. FNP-l-STP-29.5, ver 4.0

2. PCB-VOL1-CRV77, Cycle 23 rev 8

3. PCB-VOL1-CRV78, Cycle 23 rev 8

4. Unit 1, COLR for FNP Unitl Cycle 23, Rev 0 Figure 1.

5. Pen/Pencil

6. calculator Critical ELEMENT justification:

Evaluation STEP 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:

A. PRESENT CONDITIONS KEY A.1 Core Burnup 19800 IMWD/MTU A.2 Power Level. 190 I °° 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 BANKS CBA BANK RIL HEIGHT FULL OUT BANK DEMAND Full Out (229) Full Out (229) Full Out (229) 192 Full Out (229) Full Out (229) CBB 17TTTT flTTT CBC Full Out(229) CBD 167 (166-170) SDA FULL gUI SDB FULL OUT STEPS BELOW RIL_ 0 0 0 0 0 0 I II TOTAL STEPS BELOW RIL

RANGE for CBD RIL: LO: Readability of COLR RIL curve may allow allow as low as 165 steps; although this is <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 maybe 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. Page 1 of3 Revision 4 A. PRESENT CONDITIONS A.l Core Burnup... 19_80_0 ____ IMWD/MTU A.2 Power Level. 190 I % 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 STEPS BELOW BANKS HEIGHT DEMAND RIL,...- CBA FULL OUT Full Out (229) 0 CBB HTn T nTTT Full Out (229) 0 CBC Full Out(229) - Full Out (229) 0 CBD 167 (166-170) 192 0 SDA FULL UUl Full Out (229) 0 SDB FULL OUT Full Out (229) 0 TOTAL STEPS BELOW RIL

I

° I : RANGE for CBD RIL: LO: Readability of COLR RIL curve may allow allow as low as 165 steps; although this is < 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 be 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. Page lof3 Revision 4

A.4 KEY 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) A.4.a Record data in table ROD NUMBER RIL POSITION DRPI POSITION DIFFERENCE P8 167 (+3,-2) 162 5 (3-8) j B. SHUTDOWN MARGIN I5 Ii TOTAL STEPS BELOW RIL (RANGE 3-8) I I I. 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.1) and Power Level (A.2). B.2 Penalty value of rod banks below insertion limit: I 0 steps x 75 pcm/step (A.3.a) 16268 1pcm i (Curve 77 Page 1) L CJ.: :i B.3 Penalty value of individual rods below RIL which were not counted in A.3 fPr1c Iir RIL on DRPI when the BANK demand is above RIL) IS r (NGE 3-8)_L x 10 pcm/step (+)j 50 1cm (A.4.a) L (RNG 30-80)

Page 2 of 3 Revision 4 AA.a Record data in table ROD NUMBER RIL POSITION DRPI POSITION DIFFERENCE ~ P8 167 (+3,-2) 162 5 (3-8) TOTAL STEPS BELOW RIL I 5 I (RANGE 3-8) 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 B.2 Present Burnup (A. 1 ) and Power Level (A.2).

~ _~ 1r--6-2-68-...... lp:~ -:

I (Curve 77 Page 1) I Penalty value of rod banks below insertion limit: ~ steps x 75 pcm/step = (A.3.a) 1... __________.. B.3 Penalty value of individual rods below RIL which were not counted in A.3 r--~oII.I.loO""""~ RIL on DRPI when the BANK demand is above RIL) 5 (RANGE 3-8) s x 10 pcm/step = (A.4.a) r------------ I (+) 50 em: I - (RNG 30-80) - - - J ~ Page 2 of3 Revision 4

KEY B.4 Stuck / 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.l) (_)j1406 Ipcm from Curve 77 pg. 2 B.4.b Calculate worth of Stuck/untrippable rods 1 11406 I 1406 I 515 x ()1 k 1.75] + [() I x 0.75] = 515 516 (# Stuck! (B.4.a) (B.4.a) lange. to i untripp 1 [-2460.5 to -2461] + [ -1054.5 to -1055] = I [3515 0R3516] Penalized rdu VUL111 U111U1111 LULrsJUii1LIppauIc LUU, misaligned rods, rods below the insertion limit, and uncertainty: 50 6268 0 30 80 + + = [6268÷80+35I5J*0.9 2405.7 [-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 (Curve 78). B.7 Void Collapse Defect. B.8 Available Shutdown Reactivity: ( )I [__) 11634 I + (B.5) (B.6) 50 (B.7) B.9 Shutdown Margin in excess of required Shutdown Margin (B.8 Required SDM from the COLR): 1-748.7 (1, pcm () 1770 pcm = (B.8) Required SDM from the COLR (+) 50 pcm (-) 748.7 Range: -719 to -767.0 pcmi r I(+) 1021 3 Icm I

Range: 1003 tolO5l I B.l0 If B.9 is positive, THEN emergency borate per FNP-1-AOP-27.0, EMERGENCY BORATION, to establish the required shutdown margin otherwise Shutdown Margin is adequate for the Present plant condition. DATE-- Element 15-if assumes/states emergency boration completed B.5 3515 (+1, ) x 0.9 (B.4.b) md Burnup (A.1)

(-) 2432.7 range:

1 ( ) -2403 to-2451 [ill 1634 () pcm Emergency Boration IS required May also state that a Rx trip may be warranted (P&L 4.3). Signed-- element 15-if assumes/states Performed by: Emerg Boration completed Verified by: Page 3 of 3 Revision 4 1.*.*****.**~0:* ~; B.4 Stuck I Untrippable Rod penalty: B.5 (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) (-)J 1406 Ipcm from Curve 77 pg. 2 B.4.b Calculate worth of Stuckluntrippable rods [fl x (-)~ 1.75] + [(_)1 1406 (# Stucki (B.4.a) (B.4.a) misaligned rods, rods below the insertion limit, and uncertainty: (Curve 78). 3S1S (_),..!!!(~+l~,-~O)!!!!!I x 0.9 (B.4.b) =IU Burnup (A.1) x 0 75] = (_) 3S1S range: 3S1S to 3S16 1 (-)2432.7range: 1 1 ( ) -2403 to -24S1 n 1 L _ -'-____...... L-(-) 1 1634 Ipcm B.7 Void Collapse Defect. (+) 50 pcm B.8 Available Shutdown Reactivity: ()1-2432.7 l- (_)---1.1_163_4 __ + 50 (B.5) (B.6) (B.7) B.9 Shutdown Margin in excess of required Shutdown Margin (B.8 - Required SDM from the COLR): (-)748.7 Range: 1 -719 to -767.0 pcml 1,-748.7 I r - - - - - - - - - - -I 1 ( (+) 102l.3 r.m 1 a~-==~_pcm - (-) 1770 pcm (B.8) Required SDM from the COLR 1 Range: 1003 v 1 to 10S1 1..._..... ___ B.IO IfB.9 is positive, THEN emergency borate per FNP-I-AOP-27.0, EMERGENCY BORATION, to establish the required shutdown margin otherwise Shutdown Margin is adequate for the Present plant condition. DATE-- Element IS-if assumes/states emergency boration completed Signed-- element IS-if assumes/states Performed by: _ Emerg Boration completed Verified by: ________________ _ Page 3 of3 Revision 4

Westinghouse Proprietary Class 2 PCB-1-VOL1-CRV77 150 UNIT 1 CYCLE 23 CURVE 77 KEY REV.

APPROVED: 2L A ENGINEERING SUPPORT MANAGER DATE ARI-1 Rod Worth (pcm) for Shutdown Margin Calculations Burnup Range Power Level (%) (MWD/MTU) 0 10 20 30 40 60 70 80 90 100 4587 4710 4831 5071 5311 5483 5655 5792 5927 6162 6397 > 150 1000 4667 4801 4935 5180 5425 5594 5762 5905 6048 6285 6523 >1000 2000 4717 4867 5017 5267 5517 5680 5844 5995 6145 6384 6623 > 2000 3000 4755 4909 5063 5320 5578 5740 5902 6052 6201 6442 1 6683 > 3000 4000 4818 4975 5131 5396 5660 5814 5969 6113 6257 6483 6708 > 4000 5000 4767 4920 5072 5346 5619 5778 5938 6073 6208 6439 6670 > 5000 6000 4717 4865 5013 5296 5579 5743 5906 6033 6159 6395 6631 >6000 7000 4689 4827 4965 5254 5542 5714 5885 6001 6118 6355 6593 > 7000 8000 4660 4788 4916 5211 5506 5685 5864 5 Element #6 6316 6555 800QQ0. 4 5182 5480 5669 5857 5 6292 6531 > 9000 10000 4632 4742 4852 5154 5455 5652 5850 5939 6028 6268 6507 >10000 11000 4622 4725 4828 5129 5431 564f 5850 5933 6016 6253J 6490 >11000 12000 4612 4707 4803 5105 5408 5629 5850 5927 6004 6239 6473 >12000 13000 4617 4706 4795 5096 5398 5631 5865 5937 6010 6242 6475 4704 4787 5087 5387 5633 5879 5947 6015 6245 6476 >14000 15000 4631 4709 4787 5086 5385 5642 5900 5964 6028 6256 6485 >15000 16000 4641 4714 4787 5085 5382 5652 5921 5981 6041 6267 6493 >16000 17000 4662 4731 4800 5096 5391 5669 5947 6004 6062 6286 6510 >17000 18000 4682 4748 4813 5107 5400 5687 5973 6028 6083 6304 6526 >18000 19000 4709 4771 4833 5125 5418 5710 6002 6056 6109 6328 6547 >19000 20000 4735 4794 4852 5144 5435 5734 6032 6083 6135 6351 6568 >20000 20885 4760 4818 4876 5165 5454 5759 6063 6112 6161 6377 6592 >13000 14000 Notes: 1. Rod worth data assumes the starting point is rods at the Rod Insertion Limit. If a bank is below the RIL, reduce the table value by 75 pcm for each step below the RIL. 2. The rod worth data represents negative reactivity. However, STP-29.1, STP-29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP. 3. ARI-1 is defined as All Rods In -- less the most reactive rod. The SDM calculation requires that one rod be assumed stuck. Therefore, use the data directly from the table above when there are not any known stuck rods. 4621 50 Page 1 of 2 I Westinghouse Proprietary Class 2 PCB-l-VOLl-CRV77 UNIT 1 CYCLE 23 CURVE 77 /1 REV.~ APPROVED: t)(~., A: f<4f f~r P"'rt1~ t'7'-_H<!Y 1fI# ENGINEERING SUPPORT MANAGER DATE ARI-l Rod Worth (pern) for Shutdown Margin Calculations BumupRange Power Level (%) (MWD/MTU) 0 10 20 30 40 50 60 70 80 90 100 ~150 4587 4710 4831 5071 5311 5483 5655 5792 5927 I 6162 6397 > 150 ~1000 4667 4801 4935 5180 5425 5594 5762 5905 6048 6285 6523 > 1000 ~2000 4717 4867 5017 5267 5517 5680 5844 5995 6145 6384 6623 > 2000 ~3000 4755 4909 5063 5320 5578 5740 5902 6052 6201 6442 6683 > 3000 ~4000 4818 4975 5131 5396 5660 5814 5969 6113 6257 6483 6708 >4000 ~5000 4767 4920 5072 5346 5619 5778 5938 6073 6208 6439 6670 > 5000 ~6000 4717 4865 5013 5296 5579 5743 5906 6033 6159 6395 6631 > 6000 ~7000 4689 4827 4965 5254 5542 5714 5885 6001 6118 6355 6593 > 7000 ~8000 4660 4788 4916 5211 5506 5685 5864 51 Element #6 6316 6555 '> ROOO < <)000 ~--~ ~ ~ ~L 5669 5857 54 6292 6531 ~;m;_ w -- > 9000 ~10000 4632 4742 4852 5154 5455 5652 5850 5939 6028 62~ >10000 ~11000 4622 4725 4828 5129~.. ~'5r3"l

~61J.

5!SSO- -5'9~3 -6IJi6- -625: >11000 ~12000 4612 4707 4803 5105 5408 5629 5850 5927 6004 6239 6473 >12000 ~13000 4617 4706 4795 5096 5398 5631 5865 5937 6010 6242 6475 >13000 ~14000 4621 4704 4787 5087 5387 5633 5879 5947 6015 6245 6476 >14000 ~15000 4631 4709 4787 5086 5385 5642 5900 5964 6028 6256 6485 >15000 ~16000 4641 4714 4787 5085 5382 5652 5921 5981 6041 6267 6493 >16000 ~17000 4662 4731 4800 5096 5391 5669 5947 6004 6062 6286 6510 >17000 ~18000 4682 4748 4813 5107 5400 5687 5973 6028 6083 6304 6526 >18000 ~19000 4709 4771 4833 5125 5418 5710 6002 6056 6109 6328 6547 >19000 ~20000 4735 4794 4852 5144 5435 5734 6032 6083 6135 6351 6568 >20000 ~20885 4760 4818 4876 5165 5454 5759 6063 6112 6161 I 6377 6592 Notes:

1.

Rod worth data assumes the starting point is rods at the Rod Insertion Limit. If a bank is below the RIL, reduce the table value by 75 pcm for each step below the RIL.

2.

The rod worth data represents negative reactivity. However, STP-29.1, STP-29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP.

3.

ARI-1 is defined as All Rods In --less the most reactive rod. The SDM calculation requires that one rod be assumed stuck. Therefore, use the data directly from the table above when there are not any known stuck rods. Page 1 of2

Westinghouse Proprietary Class 2 PCB-1-VOL1-CRV77 UNIT 1 CYCLE 23 CURVE 77 Control Rod Worth for SDM Calculations I KEY REV. APPROVED:

cr Btyr (n ENGINEERING SUPPORT MANAGER DATE Worth of Most Reactive Rod (pcm) for Shutdown Margin Calculations Notes

Burnup Range Power Level (MWD/MTU) 0% to 100% 150 658 > 150 l000 676 >1000 2000 732 >2000 3000 781 >3000 4000 889 >4000 5000 1024 > 5000 6000 1160 > 6000 7000 1232 >7000 8000 1304 >8000 9000 1355 >11000 12000 1494 >12000 13000 1528 >13000 14000 1561 >14000 15000 1592 >15000 16000 1623 >16000 17000 1653 >17000 18000 1684 >18000 19000 1713 >19000 20000 1741 >20000 20885 1767 1. Rod worth data assumes the starting point is rods at the Rod Insertion Limit. 2. The rod worth data represents negative reactivity. However, STP-29.1, STP-29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP. 3. ARI-1 is defined as All Rods In -- less the most reactive rod. 4. For multiple stuck rods, the ARI-1 value on Page 1 of this curve should be reduced by the following calculation: [KUR x WSR x 1.75] + [WSR x 0.75] where KUR = Number of known untrippable rods (does not include rod assunied stuck in ART-i table) and WSR = Worst stuck rod (i.e. most reactive rod) element #9 ] > 9000 10000 1406 >10000 11000 1450 Page 2 of 2 Westinghouse Proprietary Class 2 PCB-l-VOLI-CRV77 REV. 8 UNIT 1 CYCLE 23 CURVE 77 Control Rod Worth for SDM Calculations

/#

APPROVED: y ~

k. f4 IN ptr"" (1'-;,1<"-

ENGINEERING SUPPORT MANAGER Lf-!5-(!1 DATE Worth of Most Reactive Rod (pcm) for Shutdown Margin Calculations BumupRange Power Level (MWD/MTU) 0% to 100%

150 658

> 150

1000 676

> 1000

2000 732

> 2000

3000 781

>3000

4000 889

>4000

5000 1024

> 5000

6000 1160

> 6000

7000 1232

> 7000 <8000 1304 I element #9 I > 8000

9000 1355 I

> 9000

10000 1406 I

>10000

11000 1450

>11000

12000 1494

>12000

13000 1528

>13000

14000 1561

>14000

15000 1592

>15000

16000 1623

>16000

17000 1653

>17000

18000 1684

>18000

19000 1713

>19000

20000 1741

>20000

20885 1767 Notes

1.

Rod worth data assumes the starting point is rods at the Rod Insertion Limit.

2.

The rod worth data represents negative reactivity. However, STP-29.1, STP-29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP.

3.

ARI-1 is defined as All Rods In -- less the most reactive rod.

4.

For multiple stuck rods, the ARl-l value on Page 1 of this curve should be reduced by the following calculation: [KUR x WSR x 1.75J + [WSR x 0.75] where KUR = Number of known untrippable rods (does not include rod assumed stuck in ARl-l table) and WSR = Worst stuck rod (i.e. most reactive rod) Page 2 of2

Westinghouse Proprietary Class 2 PCB-1-VOL1-CRV78 UNIT 1 CYCLE 23 CURVE 78 T,-1 P,-rn,. fl4r-- l,- fl1E KY REV. APPROVED: zø ENGINEERING SUPPORT MANAGER DATE Power Defect (pcm) for Shutdowit Margin Calculations Burnup Range Power Level (%) (MWD/MTU) 0 10 20 30 40 50 60 70 80 W 100 150 0 361 537 717 898 958 1019 1119 1219 j 1326 1432 > 150 1000 0 351 522 701 879 943 1006 1106 1206 1307 1409 > 1000 2000 0 330 495 667 839 903 967 1068 1169 1265 1361 > 2000 3000 0 317 476 647 818 879 941 1041 1142 1237 1332 > 3000 4000 0 326 489 664 839 901 964 1062 1161 1261 1360 > 4000 5000 0 344 514 697 879 942 1004 1103 1202 1306 1410 > 5000 6000 0 362 539 729 919 982 1045 1144 1242 1351 1459 > 6000 7000 0 388 576 774 972 1037 1103 1202 1301 1416 1531 > 7000 8000 0 414 613 818 1024 1092 1160 1260 1360 1481 1603 >8000<9000 0 440 651 863 1074 1147 1220 1lement 1558 1684 > 9000 10000 0 466 690 907 1124 1202 1280 1391 1503 1634 1765 >10000 11000 0 492 728 950 1173 1258 1344 1461 1579 1717 1854 >11000 12000 0 518 766 994 1222 1315 1408 1531 1655 1800 1944 >12000 13000 0 543 804 1035 1267 1369 1471 1603 1734 1884 2034 >13000 14000 0 567 841 1077 1313 1424 1535 1674 1813 1968 2123 >14000 15000 0 589 875 1115 1356 1477 1597 1744 1890 2054 2217 >15000 16000 0 611 908 1153 1399 1529 1660 1813 1967 2139 2310 >16000 17000 0 633 940 1189 1438 1578 1718 1882 2046 2223 2400 >17000 18000 0 654 971 1225 1478 1627 1777 1951 2125 2307 2489 >18000 19000 0 673 1001 1259 1516 1677 1837 2020 2203 2392 2582 >19000 20000 0 692 1031 1293 1554 1726 1897 2089 2280 2477 2674 >20000 20885 0 709 1057 1323 1590 1771 1953 2152 2351 2554 2757 Notes: 1. STP-29.1, STP-29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP. I Westinghouse Proprietary Class 2 PCB-I-VOLI-CRV78 UNlT 1 CYCLE 23 CURVE 78 T~9tal,pOJA7er Defect for SQM CatfJl1atjops REV. '6 APPROVED: ~<t" fWtJ j"y pry(j#, 4..-,,,,,.-,1# ENGINEERING SUPPORT MANAGER DATE Power Defect (pern) for Shutdown Margin Calculations Bumup Range Power Level (%) (MWD/MTU) 0 10 20 30 40 50 60 70 80 9U 100 ~150 0 361 537 717 898 958 1019 1119 1219 1326 1432 > 150 ~1000 0 351 522 701 879 943 1006 1106 1206 1307 1409 > 1000 ~2000 0 330 495 667 839 903 967 1068 1169 1265 I 1361 >2000 ~3000 0 317 476 647 818 879 941 1041 1142 1237 1332 >3000 ~4000 0 326 489 664 839 901 964 1062 1161 1261 1360 >4000 ~ 5000 0 344 514 697 879 942 1004 1103 1202 1306 1410 > 5000 ~6000 0 362 539 729 919 982 1045 1144 1242 1351 I 1459 I > 6000 ~7000 0 388 576 774 972 1037 1103 1202 1301 1416 ! 1531 I > 7000 ~8000 0 414 613 818 1024 1092 1160 1260 1360 1481 1603 > 'woo < QOOO 0 440 651 863 1074 ,Jl7!~, 1220 JElement #12 I 1558 1684

0

> 9000 ~10000 0 466 690 907 1124 1202 1280 1391 1503 1634 176511 >10000 ~11000 0 492 728 950 1173 1258 1344 1461 1579 1717 1854 >11000 ~12000 0 518 766 994 1222 1315 1408 1531 1655 1800 1944 >12000 ~13000 0 543 804 1035 1267 1369 1471 1603 1734 1884 2034 >13000 ~14000 0 567 841 1077 1313 1424 1535 1674 1813 1968 2123 >14000 ~15000 0 589 875 1115 1356 1477 1597 1744 1890 2054 2217 >15000 ~16000 0 611 908 1153 1399 1529 1660 1813 1967 2139 2310 >16000 ~17000 0 633 940 1189 1438 1578 1718 1882 2046 2223 2400 >17000 ~18000 0 654 971 1225 1478 1627 1777 1951 2125 2307 2489 >18000 ~19000 0 673 1001 1259 1516 1677 1837 2020 2203 2392 2582 >19000 ~20000 0 692 1031 1293 1554 1726 1897 2089 2280 2477 2674 >20000 ~20885 0 709 1057 1323 1590 1771 1953 2152 2351 2554 2757 Notes:

1.

STP-29.1, STP-29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP.

COLR for FNP Unit 1 Cycle 23 Revision 0 Page 10 of 13 150 Figure 1 Rod Bank Insertion Limits versus Rated ThwrmI Power KEY C 200 175 C

o. 125 U)

C0 100 00 C 0 75 50 25 0 Elements 4 & 5 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. COLR for FNP Unit 1 Cycle 23 Revision 0 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power 200 175 '2

== 150 ~ "C .r:... ;: ~ 125 2 !2 s:: 0 E f/) 0 c.. s:: cu llJ "C 0 0::: 100 75 50 25 o 0.0 1.1' II" (0,114) r- / 0.1 i'."'" ','i'd.",,".' i',..' "'!'TY"!'(T ","i"i" 1...- (.552,225) II" 1"'- II" ~ II"

':' :,;~ :':"

I:':-J"~\\ 'OC' Banke 1.1 !.I I I I I I !.I I I I I I y =( 187 - 0,000 )0,900 _ 0,070)+ 0,000 1.00-0,070 l.I' y = 166.9 (rounded using 4signficant digits) !.I => 167sleps if not calculated and only read from graph then> 165 And < 170; Therefore Half the accuracy of the scale !.I => 167,5 !.I BankO !.I !.I 1.1 II" (.070,0) I I I I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 Fraction of RATED THERMAL POWER Page 10 of 13 '~'., (1,187) _ 1.1 II" .1: ,S J 1 1 i ~ 0.9 1.0 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.

FNPHLT-33ADMIN A.21.A HANDOUT Pg 1 of I CONDITIONS When I tell you to begin, you are to Determine if Shutdown Margin is adequate using STP-29.5, SHUTDOWN MARGIN CALCULATION IN MODES 1 AND 2 (TAVG 547°F), for Unit 1. The conditions under which this task is to be performed are: a. Unit 1 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, 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. Core burnup is 9,800 MWD/MTU burnup. h. FNP-1-STP-29.5, SHUTDOWN MARGTN CALCULATION IN MODES I AND 2 (TAVG 547°F), initial conditions are satisfied. i. The Shift Supervisor has directed you to complete FNP-1-STP-29.5 starting at step 5.1 and identify whether or not emergency boration is required. FNP HL T-33 ADMIN A.2.1.A HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to Determine if Shutdown Margin is adequate using STP-29.5, SHUTDOWN MARGIN CALCULATION IN MODES 1 AND 2 (TAVG 2: 547°F), for Unit 1. The conditions under which this task is to be performed are:

a. Unit 1 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, HI4, F6, FlO, KIO, 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. Core burnup is 9,800 MWDIMTU burnup.

h. FNP-I-STP-29.5, SHUTDOWN MARGIN CALCULATION IN MODES 1 AND 2 (TAVG 2:

547°F), initial conditions are satisfied.

i. The Shift Supervisor has directed you to complete FNP-I-STP-29.5 starting at step 5.1 and identify whether or not emergency boration is required.

06/18/01 10:31:04 FNP-1-STP-29.5 April 21, 2000 Revision 4 FARLEY NUCLEAR PLANT SURVEILLANCE TEST PROCEDURE FNP-1 -STP-29.5 S A F E T Y SHUTDOWN MARGIN CALCULATION IN MODES 1 AND 2 (TAVG 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 4-27-00 06118/01 10:31 :04 FARLEY NUCLEAR PLANT SURVEILLANCE TEST PROCEDURE FNP-I-STP-29.5 FNP-I-STP-29.5 April 21, 2000 Revision 4 SHUTDOWN MARGIN CALCULATION IN MODES 1 AND 2 (TAVG 2 547°F) 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-'--=-27=---"-00"--_____ _ S A F E T Y R E L A T E D

06I18/0 10:31:04 FNP-1-STP-29.5 FARLEY NUCLEAR PLANT SURVEILLANCE TEST REVIEW SHEET SURVEILLANCE TEST NO. TECHNICAL SPECIFICATION REFERENCE 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 1 AND 2 1 *,2* (TAVG 547°F)

See special test exceptions of above specifications TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER)

PERFORMED BY 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 []The following deficiencies occurred: [] Corrective action taken or initiated: SHIFT FOREMAN REVIEW REVIEWED BY___________________________________ DATE. []Procedure properly completed and satisfactory []Comments: TECHNICAL GROUP REACTOR ENG REVIEW REVIEWED BY DATE_______________ [1 Satisfactory and Approved [1 Comments: Revision 4 06118/01 10:31:04 FNP-1-STP-29.5 F ARLEY NUCLEAR PLANT SURVEILLANCE TEST REVIEW SHEET SURVEILLANCE TEST NO. TECHNICAL SPECIFICATION REFERENCE FNP-I-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 1 AND 2 1 *,2* (TAVG ;;:: 547°F)

See special test exceptions of above specifications TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER)

PERFORMED BY DATE/TIME COMPONENT OR TRAIN TESTED (if applicable) [ ] ENTIRE STP PERFORMED [ ] FOR SURVEILLANCE CREDIT [] PARTIAL STP PERFORMED: [] NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL: TEST COMPLETED: [ ] Satisfactory [ ] Unsatisfactory [ ] The following deficiencies occurred: [ ] Corrective action taken or initiated: SHIFT FOREMAN REVIEW REVIEWED BY DATE [ ] Procedure properly completed and satisfactory [ ] Comments: TECHNICAL GROUP-REACTOR ENG REVIEW REVIEWED BY DATE [ ] Satisfactory and Approved [ ] Comments: Revision 4

06/18/01 10:31:04 FNP-1-STP-29.5 TABLE OF CONTENTS Procedure Contains Number of Pages Body 2 Shutdown Margin 3 STRS 1 Page 1 of 1 Revision 4 06/18/01 10:31:04 FNP-1-STP-29.5 TABLE OF CONTENTS Procedure Contains Number of Pages Body......................................................... 2 Shutdown Margin..................................... 3 STRS........................................................ 1 Page 1 of 1 Revision 4

06/18/01 10:31:04 FNP-1-STP-29.5 FARLEY NUCLEAR PLANT UNIT 1 SURVEILLANCE TEST PROCEDURE STP-29.5 SHUTDOWN MARGIN CALCULATION IN MODES 1 AND 2 (TAVG 547°F) 1.0 Purpose 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 as directed by Technical Specifications in Modes 1 or 2: 1.1.1 One or more rod(s) untrippable (LCO 3.1.4), 1.1.2 One or more rod(s) not aligned within 12 steps of their group step counter 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), 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 TAVG5 4 7°F. HBF 3.3 TAVG +/- 1 °F of programmed value. (Needed for Power Defect to be accurate) HBF 34 The plant is in Mode 1 or 2 with Keff 1. HBF Technical Specifications required action entered to verify SDM to be within the limits provided in the COLR QE Shift Supervisor desires to perform. Revision 4 06118/01 10:31:04 FNP-I-STP-29.5 F ARLEY NUCLEAR PLANT UNIT 1 SURVEILLANCE TEST PROCEDURE STP-29.5 SHUTDOWN MARGIN CALCULATION IN MODES 1 AND 2 (TAVG ~ 547°F) 1.0 Purpose 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 as directed by Technical Specifications in Modes 1 or 2: 1.1.1 One or more rod(s) untrippable (LCO 3.1.4), 1.1.2 One or more rode s) not aligned within 12 steps of their group step counter 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), 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 HBF 3.2 HBF 3.3 HBF 3.4 HBF 3.5 The revision of this procedure has been verified to be the current revision and correct unit for the task. (OR 1-98-498) TAVG +/- 1°F of programmed value. (Needed for Power Defect to be accurate) The plant is in Mode 1 or 2 with Keff ~ 1. Technical Specifications required action entered to verify SDM to be within the limits provided in the COLR OR Shift Supervisor desires to perform. Revision 4

06/18/01 10:31:04 FNP-1-STP-29.5 4.0 Precautions and Limitations 4.1 Read all curves as accurately as possible OR most conservatively. 4.2 Observe proper algebraic sign notation throughout the calculation. 4.3 IF necessary to emergency borate due to inadequate shutdown margin, THEN consideration should be given to tripping the reactor and entering FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION concurrent with the emergency 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.
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 06118/01 10:31:04 FNP-1-STP-29.5 4.0 Precautions and Limitations 4.1 Read all curves as accurately as possible OR most conservatively. 4.2 Observe proper algebraic sign notation throughout the calculation. 4.3 IF necessary to emergency borate due to inadequate shutdown margin, THEN consideration should be given to tripping the reactor and entering FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION concurrent with the emergency 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.
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

06/18/01 10:31:04 FNP-1-STP-29.5 SHUTDOWN MARGIN IN MODES 1 AND 2 A. PRESENT CONDITIONS A. 1 Core Burnup MWD/MTU A.2 Power Level. A.3 Determine number of penalty steps for ROD BANKS below RIL. (Use COLR or convert the RJL computer reading from % to steps) A.3.a Record data in table ROD 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 Page 1 of 3 Revision 4 06118/0110:31:04 FNP-l-STP-29.5 SHUTDOWN MARGIN IN MODES 1 AND 2 A. PRESENT CONDITIONS A.l MWDIMTU Core Burnup A.2 Power Level. 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 STEPS BELOW BANKS HEIGHT DEMAND RIL CBA FULL OUT CBB FULL OUT CBC CBD SDA FULL OUT SDB FULL OUT TOTAL STEPS BELOW RIL '- ________.1 Page 1 of3 Revision 4

06/18/01 10:31:04 FNP-1-STP-29.5 A.4 Determine number of penalty steps for RODS below 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 Present Burnup (A.1) and Power Level (A.2). () i (Curve 77 Page 1) L. B.2 Penalty value of rod banks below insertion limit: x 75 pcm/step = () P (A.3.a) L B.3 Penalty value of individual rods below RIL which were not counted in A.3 (Rods below RIL on DRPI when the BANK demand is above RIL) I (+) pcm x 10 pcm/step = (A.4.a) Page 2 of 3 Revision 4 06/18/01 10:31 :04 FNP-1-STP-29.5 A.4 Determine number of penalty steps for RODS below RlL 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 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. 1 ) and Power Level (A.2). B.2 Penalty value of rod banks below insertion limit: ___ steps x 75 pcm/step (A.3.a) r - - - - - - - - - - -, , (-) pcm (Curve 77 Page 1), 1... __________... , (+) pcm,, L __________... B.3 Penalty value of individual rods below RIL which were not counted in A.3 (Rods below RlL on DRPI when the BANK demand is above RIL) ___ steps X 10 pcm/step (A.4.a) Page 2 of3 r------------ , (+) pcm' ____________ 1 Revision 4

06/18/01 10:31:04 FNP-1-STP-29.5 B.4 Stuck / 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 B.4.b Calculate worth of Stuck!untrippable rods [ x () x 1.75] + [() x 0.75] = () (# Stuck/ (B.4.a) (B.4.a) untrippable rods) (Most reactive (Most reactive rod worth) rod worth) B.5 Penalized rod worth considering stuckluntrippable rods, misaligned rods, rods below the insertion limit, and uncertainty: [(-) + + (-)_____ x 0.9 I () pcm (B.1) (B.2) (B.3) (B.4.b) L B.6 Power Defect at Power Level (A.2) and Burnup (A.1) (Curve 78). () B.7 Void Collapse Defect. (+) 50 pcm B.8 Available Shutdown Reactivity: I ()_______ ()__________ + 50 pcmj (B.5) (B.6) (B.7) B.9 Shutdown Margin in excess of required Shutdown Margin (B.8 Required SDM from the COLR): I ()__________ pcm () 1770 pcm () (B.8) Required SDM i (SDMEXCeSS) fromtheCOLR L B.10 If B.9 is positive, THEN emergency borate per FNP-1-AOP-27.0, EMERGENCY BORATION, to establish the required shutdown margin otherwise Shutdown Margin is adequate for the Present plant condition. Date:____________________ Performed by: Date:___________________ Verified by: Page 3 of 3 Revision 4 06118/01 10:31:04 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 B.4.b Calculate worth of Stuckluntrippable rods x (-) x 1.7S] + [(-) x 0.7S] = (-) ___ pcm B.S B.6 B.7 (# Stucki (B.4.a) (B.4.a) untrippable rods) (Most reactive (Most reactive rod worth) rod worth) Penalized rod worth considering stuckluntrippable rods, misaligned rods, rods below the insertion limit, and uncertainty: [(-.1-) ___ + __ + - (-) 1 x 0.9 (B.1) (B.2) (B.3) (B.4.b) Power Defect at Power Level (A.2) and Burnup (A. 1) (Curve 78). Void Collapse Defect. B.8 Available Shutdown Reactivity: ()--- (B.5) 1 _____ + (B.6) so (B.7) B.9 Shutdown Margin in excess of required Shutdown Margin (B.8 - Required SDM from the COLR): O ____ pcm (-) 1770 pcm (B.8) Required SDM from the COLR ( ( ( ( ) pcm ( L __________ _ (-) ____ pcm (+) _--'S"-"O'---_pcm (- - - - - - - - - - -, ( ( L ______ __ ~c~ ~ r - - - - - - - - - - -(

()

pcm (SDMExcess) ( L... __________ _ B.10 IfB.9 is positive, THEN emergency borate per FNP-1-AOP-27.0, EMERGENCY BORATION, to establish the required shutdown margin otherwise Shutdown Margin is adequate for the Present plant condition. Date: Performed by: _______________ _ Date: Verified by: _______________ _ Page 3 of3 Revision 4

Westinghouse Proprietary Class 2 PCB-1-VOL1-CRV77 UNIT 1 CYCLE 23 CURVE 77 Control Rod Worth for SDM Calculations REV.___ APPROVED: f r kya.i ENGINEERING SUPPORT MANAGER DATE ART-i Rod Worth (pcm) for Shutdown Margin Calculations Burnup Range Power Level (%) (MWDIMTU) 0 10 20 30 40 50 60 70 80 90 100 150 4587 4710 4831 5071 5311 5483 5655 5792 5927 6162 6397 > 150 1000 4667 4801 4935 5180 5425 5594 5762 5905 6048 6285 6523 >1000 2000 4717 4867 5017 5267 5517 5680 5844 5995 6145 6384 6623 > 2000 3000 4755 4909 5063 5320 5578 5740 5902 6052 6201 6442 6683 >3000 4000 4818 4975 5131 5396 5660 5814 5969 6113 6257 6483 6708 > 4000 5000 4767 4920 5072 5346 5619 5778 5938 6073 6208 6439 6670 >5000 6000 4717 4865 5013 5296 5579 5743 5906 6033 6159 6395 6631 >6000 S 7000 4689 4827 4965 5254 5542 5714 5885 6001 6118 6355 6593 > 7000 8000 4660 4788 4916 5211 5506 5685 5864 5970 6076 6316 6555 >8000 59000 4646 4765 4884 5182 5480 5669 5857 5955 6052 6292 6531 > 9000 510000 4632 4742 4852 5154 5455 5652 5850 5939 6028 6268 6507 >10000 511000 4622 4725 4828 5129 5431 5641 5850 5933 6016 6253 6490 >11000 512000 4612 4707 4803 5105 5408 5629 5850 5927 6004 6239 6473 >12000 513000 4617 4706 4795 5096 5398 5631 5865 5937 6010 6242 6475 >13000 514000 4621 4704 4787 5087 5387 5633 5879 5947 6015 6245 6476 >14000 515000 4631 4709 4787 5086 5385 5642 5900 5964 6028 6256 6485 >15000 516000 4641 4714 4787 5085 5382 5652 5921 5981 6041 6267 6493 >16000 17000 4662 4731 4800 5096 5391 5669 5947 6004 6062 6286 6510 >17000 518000 4682 4748 4813 5107 5400 5687 5973 6028 6083 6304 6526 >18000 519000 4709 4771 4833 5125 5418 5710 6002 6056 6109 6328 6547 >19000 20000 4735 4794 4852 5144 5435 5734 6032 6083 6135 6351 6568 >20000 20885 4760 4818 4876 5165 5454 5759 6063 6112 6161 6377 6592 Notes: 1. Rod worth data assumes the starting point is rods at the Rod Insertion Limit. If a bank is below the RIL, reduce the table value by 75 pcm for each step below the RIL. 2. The rod worth data represents negative reactivity. However, STP-29.1, STP-29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP. 3. ARI-1 is defined as All Rods In -- less the most reactive rod. The SDM calculation requires that one rod be assumed stuck. Therefore, use the data directly from the table above when there are not any known stuck rods. Page 1 of 2 BumupRange (MWDIMTU) ~150 >150 ~1000 > 1000 ~2000 > 2000 ~3000 > 3000 ~4000 >4000 ~5000 > 5000 ~6000 > 6000 ~7000 > 7000 ~8000 > 8000 ~9000 > 9000 ~10000 >10000 ~11000 >11000 ~12000 >12000 ~13000 >13000 ~14000 >14000 ~15000 >15000 ~16000 >16000 ~17000 >17000 ~18000 >18000 ~19000 >19000 ~20000 >20000 ~20885 Notes: REV.~ Westinghouse Proprietary Class 2 UNIT 1 CYCLE 23 CURVE 77 Control Rod Worth for SDM Calculations APPROVED: tj(~ J:. (<<.; Iv,- PI-Yo", ?'?r,n"/V 7J# ENGINEERING SUPPORT MANAGER PCB-l-VOL1-CRV77 DATE ARI-l Rod Worth (pcm) for Shutdown Margin Calculations Power Level (%) 0 10 20 30 40 50 60 70 80 90 100 4587 4710 4831 5071 5311 5483 5655 5792 5927 6162 6397 4667 4801 4935 5180 5425 5594 5762 5905 6048 6285 6523 4717 4867 5017 5267 5517 5680 5844 5995 6145 6384 6623 4755 4909 5063 5320 5578 5740 5902 6052 6201 6442 6683 4818 4975 5131 5396 5660 5814 5969 6113 6257 6483 6708 4767 4920 5072 5346 5619 5778 5938 6073 6208 6439 6670 4717 4865 5013 5296 5579 5743 5906 6033 6159 6395 6631 4689 4827 4965 5254 5542 5714 5885 6001 6118 6355 6593 4660 4788 4916 5211 5506 5685 5864 5970 6076 6316 6555 4646 4765 4884 5182 5480 5669 5857 5955 6052 6292 6531 4632 4742 4852 5154 5455 5652 5850 5939 6028 6268 6507 4622 4725 4828 5129 5431 5641 5850 5933 6016 6253 6490 4612 4707 4803 5105 5408 5629 5850 5927 6004 6239 6473 4617 4706 4795 5096 5398 5631 5865 5937 6010 6242 6475 4621 4704 4787 5087 5387 5633 5879 5947 6015 6245 6476 4631 4709 4787 5086 5385 5642 5900 5964 6028 6256 6485 4641 4714 4787 5085 5382 5652 5921 5981 6041 6267 6493 4662 4731 4800 5096 5391 5669 5947 6004 6062 6286 6510 4682 4748 4813 5107 5400 5687 5973 6028 6083 6304 6526 4709 4771 4833 5125 5418 5710 6002 6056 6109 6328 6547 4735 4794 4852 5144 5435 5734 6032 6083 6135 6351 6568 4760 4818 4876 5165 5454 5759 6063 6112 6161 6377 6592

1.

Rod worth data assumes the starting point is rods at the Rod Insertion Limit. If a bank is below the RIL, reduce the table value by 75 pcm for each step below the RIL.

2.

The rod worth data represents negative reactivity. However, STP-29.1, STP-29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP.

3.

ARI-l is defined as All Rods In -- less the most reactive rod. The SDM calculation requires that one rod be assumed stuck. Therefore, use the data directly from the table above when there are not any known stuck rods. Page 1 of2

Westinghouse Proprietary Class 2 PCB-1-VOL1-CRV77 UNIT 1 CYCLE 23 CURVE 77 Control Rod Worth for SDM Calculations REV. APPROVED: fi ENGINEERING SUPPORT MANAGER DATE Worth of Most Reactive Rod (pcm) for Shutdown Margin Calculations Burnup Range Power Level (MWD/MTU) 0% to 100% 150 658 > 150 1000 676 >1000 2000 732 > 2000 3000 781 > 3000 4000 889 >4000 5000 1024 > 5000 6000 1160 > 6000 7000 1232 > 7000 8000 1304 > 8000 9000 1355 > 9000 10000 1406 >10000 11000 1450 >11000 12000 1494 >12000 13000 1528 >13000 14000 1561 >14000 15000 1592 >15000 16000 1623 >16000 17000 1653 >17000 18000 1684 >18000 19000 1713 >19000 20000 1741 >20000 20885 1767 Notes: 1. Rod worth data assumes the starting point is rods at the Rod Insertion Limit. 2. The rod worth data represents negative reactivity. However, STP-29.1, STP29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP. 3. AR1-1 is defined as All Rods In -- less the most reactive rod. 4. For multiple stuck rods, the ARI-1 value on Page 1 of this curve should be reduced by the following calculation: [KUR x WSR x 1.75] + {WSR x 0.75] where KUR = Number of known untrippable rods (does not include rod assumed stuck in ART-i table) and WSR = Worst stuck rod (i.e. most reactive rod) Page 2of2 Westinghouse Proprietary Class 2 PCB-I-VOLl-CRV77 REV.~ UNIT I CYCLE 23 CURVE 77 Control Rod Worth for SDM Calculations ~ APPROVED: y ~ A: f.ty Ie'r $trlIi'l fU:'Hr ENGINEERING SUPPORT MANAGER 1.(-/5 ~O, DATE Worth of Most Reactive Rod (pcm) for Shutdown Margin Calculations Burnup Range Power Level (MWD/MTU) 0% to 100% ~150 658 > 150 ~1000 676 > 1000 ~2000 732 > 2000 ~3000 781 > 3000 ~4000 889 >4000 ~5000 1024 > 5000 ~6000 1160 > 6000 ~7000 1232 > 7000 ~8000 1304 > 8000 ~9000 1355 > 9000 ~10000 1406 >10000 ~11000 1450 >11000 ~12000 1494 >12000 ~13000 1528 >13000 ~14000 1561 >14000 ~15000 1592 >15000 ~16000 1623 >16000 ~17000 1653 >17000 ~18000 1684 >18000 ~19000 1713 >19000 ~20000 1741 >20000 ~20885 1767 Notes:

1.

Rod worth data assumes the starting point is rods at the Rod Insertion Limit.

2.

The rod worth data represents negative reactivity. However, STP-29.1, STP-29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP.

3.

ARI-1 is defined as All Rods In --less the most reactive rod.

4.

For multiple stuck rods, the ARI-l value on Page 1 of this curve should be reduced by the following calculation: [KUR x WSR x 1.751 + [WSR x 0.75] where KUR = Number of known untrippable rods (does not include rod assumed stuck in ARI-l table) and WSR = Worst stuck rod (i.e. most reactive rod) Page 2 of 2

Westinghouse Proprietary Class 2 PCB-1-VOLI-CRV78 UNIT 1 CYCLE 23 CURVE 78 Total Power Defect for SDM Calculations REV. APPROVED: ENGINEERING SUPPORT MANAGER DATE Power Defect (pcm) for Shutdown Margin Calculations Burnup Range Power Level (%) (MWD/MTU) 0 10 20 30 40 50 60 70 80 90 100 150 0 361 537 717 898 958 1019 1119 1219 1326 1432 > 150 1000 0 351 522 701 879 943 1006 1106 1206 1307 1409 > 1000 2000 0 330 495 667 839 903 967 1068 1169 1265 1361 > 2000 3000 0 317 476 647 818 879 941 1041 1142 1237 1332 > 3000 4000 0 326 489 664 839 901 964 1062 1161 1261 1360 > 4000 5000 0 344 514 697 879 942 1004 1103 1202 1306 1410 > 5000 6000 0 362 539 729 919 982 1045 1144 1242 1351 1459 > 6000 7000 0 388 576 774 972 1037 1103 1202 1301 1416 1531 > 7000 8000 0 414 613 818 1024 1092 1160 1260 1360 1481 1.603 >8000 9000 0 440 651 863 1074 1147 1220 1326 1431 1558 1684 >9000 10000 0 466 690 907 1124 1202 1280 1391 1503 1634 1765 >10000 11000 0 492 728 950 1173 1258 1344 1461 1579 1717 1854 >11000 12000 0 518 766 994 1222 1315 1408 1531 1655 1800 1944 >12000 13000 0 543 804 1035 1267 1369 1471 1603 1734 1884 2034 >13000 14000 0 567 841 1077 1313 1424 1535 1674 1813 1968 2123 >14000 15000 0 589 875 1115 1356 1477 1597 1744 1890 2054 2217 >15000 16000 0 611 908 1153 1399 1529 1660 1813 1967 2139 2310 >16000 17000 0 633 940 1189 1438 1578 1718 1882 2046 2223 2400 >17000 18000 0 654 971 1225 1478 1627 1777 1951 2125 2307 2489 >18000 19000 0 673 1001 1259 1516 1677 1837 2020 2203 2392 2582 >19000 20000 0 692 1031 1293 1554 1726 1897 2089 2280 2477 2674 >20000 20885 0 709 1057 1323 1590 1771 1953 2152 2351 2554 2757 Notes: 1. STP-29.1, STP-29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP. Westinghouse Proprietary Class 2 PCB-I-VOLI-CRV78 UNIT 1 CYCLE 23 CURVE 78 Total Power Defect for SDM Calculations REV.~ APPROVED: ~.t'" (u,,' (fry(}#. Crr'<1t'r "/# ENGINEERING SUPPORT MANAGER Power Defect (pem) for Shutdown Margin Calculations Bumup Range Power Level (%) (MWD/MTU) 0 10 20 30 40 50 60 70 80 90 100

150 0

361 537 717 898 958 1019 1119 1219 1326 1432 > 150

1000 0

351 522 701 879 943 1006 1106 1206 1307 1409 >1000

2000 0

330 495 667 839 903 967 1068 1169 1265 1361 >2000

3000 0

317 476 647 818 879 941 1041 1142 1237 1332 >3000

4000 0

326 489 664 839 901 964 1062 1161 1261 1360 >4000

5000 0

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 0

388 576 774 972 1037 1103 1202 1301 1416 1531 > 7000

8000 0

414 613 818 1024 1092 1160 1260 1360 1481 1603 > 8000

9000 0

440 651 863 1074 1147 1220 1326 1431 1558 1684 > 9000 510000 0 466 690 907 1124 1202 1280 1391 1503 1634 1765 >10000

11000 0

492 728 950 1173 1258 1344 1461 1579 1717 1854 >11000

12000 0

518 766 994 1222 1315 1408 1531 1655 1800 1944 >12000

13000 0

543 804 1035 1267 1369 1471 1603 1734 1884 2034 >13000

14000 0

567 841 1077 1313 1424 1535 1674 1813 1968 2123 >14000

15000 0

589 875 1115 1356 1477 1597 1744 1890 2054 2217 >15000

16000 0

611 908 1153 1399 1529 1660 1813 1967 2139 2310 >16000

17000 0

633 940 1189 1438 1578 1718 1882 2046 2223 2400 >17000

18000 0

654 971 1225 1478 1627 1777 1951 2125 2307 2489 >18000

19000 0

673 1001 1259 1516 1677 1837 2020 2203 2392 2582 >19000

20000 0

692 1031 1293 1554 1726 1897 2089 2280 2477 2674 >20000

20885 0

709 1057 1323 1590 1771 1953 2152 2351 2554 2757 Notes:

1.

STP-29.1, STP-29.2 and STP-29.5 have been written to handle the correct sign convention when the above data is entered as a positive number. Enter the above numbers directly into the STP.

CQLR for FNP Unit 1 Cycle 23 Revision 0 Page 10 of 13 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn 225 to 231 steps, inclusive 225

: : : : :i:I: : : :

- (.552, 225) 200 (1,187)_ 175 0 _BankC j 150 .125 (I, (0,114) 100 0. BankD 0.1 °l?l 0.3 0.4 05 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. COLR for FNP Unit 1 Cycle 23 Revision 0 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 HE 1 1 1 I I I L (.552,225) ~ 200 ~ 175 I.... i.I' Banke '2

= 150

~ i.I' 101' II "C .l: -;: 1/ i.I' II ~ 125 II .s ~ c: 0 (0,114) II 'iii 100 0 a. t.... i.I' Bank D c: ra co "C 0 0:: 75 1/ 50 1/ V' L 25 ~ (.070,0) ~ o I I I I I 0.0 0.1 0.2 0,3 0.4 0.5 0.6 0.7 0.8 Fraction of RATED THERMAL POWER Page 10 of 13 (1,187) _ V' 1/ 0.9 1.0 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 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 Page 1 of 5 A.3.1.R Radiation Control ADMIN G2.3.9 RO CRO-A.3. 1.R TITLE: Calculate the Maximum Permissible Stay Time within Emergency Dose Limits. PROGRAM APPLICABLE: SOT SOCT____ OLT X LOCT____ ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL 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 1 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 1 through 3 Determine if a Repair team would exceed equipment protection emergency dose limits 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 L1 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary) EXAMINER: Developer Howard Fitzwater 1 1/06/09 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP HLT-33 ADMIN Page 1 of 5 A.3.1.R Radiation Control ADMIN G2.3.9 - RO CRO-A.3.1.R TITLE: Calculate the Maximum Permissible Stay Time within Emergency Dose Limits. PROGRAM APPLICABLE: SOT SOCT OLT ---.2L LOCT __ ACCEPTABLE EVALUATION METHOD: --.L PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM ~ CLASSROOM PROJECTED TIME: 20 MIN SIMULATORIC NUMBER: NIA ALTERNATE PATH TIME CRITICAL PRA" __ lPM 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 1 through 7 may be evaluated by reviewing the responses on the Handout.

TASK STANDARD: Required for successful completion of this lPM: Calculate dose expected for Tasks 1 through 3 Determine if a Repair team would exceed equipment protection emergency dose limits ofEIP-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 0 U nsatisfactorv 0 Evaluator Comments (attach additional sheets if necessary) EXAMINER: _________ _ Howard Fitzwater 11106/09 SEE NUREG 1021 FORM ES-301-3

FNP HLT-33 ADMIN A.3.1.R Page 2 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. 1A RHR pump is air bound and must be vented per AOP-12, Attachment 1, RHR Pump Venting. c. The TSC has requested that lB RHR pump motor bearing oil levels be checked and filled as required after restoring 1A RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 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: 0 0 Calculate the expected dose for tasks 1 through 3 and document in the table. 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.

Task Time allowed! Dose Location/Task description reqd Rate Dose (minutes) (R!hr) 1 83 1A RHR Pump and HX rooms! Vent rig installation and 30 5 31 venting 2 too piping penetration room! Vent rig installation and 15 75 venting 121 piping penetration room! Vent rig installation and venting Inspect lB RHR pump motor bearing oil levels and fill as 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 may begin. FNP HLT-33 ADMIN A.3.1.R CONDITIONS Page 2 of5 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. lA RHR pump is air bound and must be vented per AOP-12, Attachment 1, RHR Pump Venting.

c. The TSC has requested that 1 B RHR pump motor bearing oil levels be checked and filled as required after restoring lA RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 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:

o Calculate the expected dose for tasks 1 through 3 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.

Task Location/Task description Time allowed/ req'd Dose Rate Dose 1 83' lA RHR Pump and HX rooms/ Vent rig installation and 2 3 4 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 may begin."

FNP HLT-33 ADMIN A.3.1.R Page 3 of 5 EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS: (CIRCLE) START TIME (30min)x 5.3 1R/hr x( lhr = 2.66REM 60 mm)

b. Task #2

c. Task #3 (20min)x 5.65R / hr x(

lhr =1.88REM 60min)

1) Calculates (in REM) a.

2.66 {Range 2.6 to 2.7) S I U b. 4.938 {4.9 to 5.0} S / U c. 1.88 {1.8to 1.9} S/U 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.

2. Evaluates exposure within 10 REM for

2) Circles YES on handout OR S I U completion of tasks 1 through 3.

states that all tasks can be completed. a. Summation of Task 1 through 3 1OREM (2.66 + 4.94 + 1.88)REM 0 a. 10 R is limit 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 1

hr V60min time is 4.5 mins (0.52Rem, II 1=4.493mm 7REM,A hr ) 1 {Range: 3 mm to 6 min} RANGE :3mmnto6min 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.

1. Determine the dose received for tasks 1 through 3.

a. Task#1 (l5min)x 19.75R/hrx lhr

= 4.938REM k60mmn) FNP HLT-33 ADMIN A.3.1.R Page 3 of5 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME

1. Determine the dose received for tasks 1 through 3. 1) Calculates (in REM)

a. Task #1

a. 2.66

{Range 2.6 to 2.7} S I U (30min)x5.31Rlhrx( Ihr. )=2.66REM 60mm

b. Task #2

b. 4.938 {4.9 to 5.0}

S I U (15min)xI9.75Rlhrx( Ihr. )=4.938REM 60mm

c. Task #3 (20min)x 5.65RI hr x( Ihr. ) = 1.88REM

c. 1.88

{1.8 to 1.9} S I U 60mm NOTE: A Cue may be required to obtain responses for each element if the candidate does not c1earl document results. Provide the Cue as stated on the Handout.

2. Evaluates exposure within 10 REM for completion of tasks 1 through 3.

a.

Summation of Task 1 through 3 1 OREM - (2.66 + 4.94 + 1.88 )REM ~ 0 0.52REM~0

b.

Determines all tasks can be completed.

3. Calculates stay time for task #4.

(0.52Rem{ hr )(60min) = 4.493 min \\ 7 REM hr {RANGE: 3 min_to _ 6min} STOP TIME

2) Circles YES on handout -OR-states that all tasks can be completed.

a.

10 R is limit

b. 0.52 R remains available

c. Circles the YES choice

3) Documents or States: STAY time is 4.5 mins

{Range: 3 min to 6 min} Terminate when all elements of the task have been completed. S/U S I U CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNP HLT-33 ADMIN A.3.1.R Page 4 of 5 GENERAL

REFERENCES:

1. FNP-0-EIP-14.0, ver 22 2. FNP-0-M-1.0,ver 18.0 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. 2. Calculator 3. pens/pencils 4. Scrap paper Critical ELEMENT justification: STEP Evaluation l.a CRITICAL - Task Objective 1.b CRITICAL - Task Objective 1.c CRITICAL - Task Objective 2 CRITICAL - Task Objective 3 CRITICAL - Task Objective COMMENTS: FNP HL T -33 ADMIN GENERAL

REFERENCES:

1. FNP-0-EIP-14.0, ver 22

2. FNP-O-M-l.O, ver 18.0

3. KA: G2.3.4 RO 3.2 GENERAL TOOLS AND EQUIPMENT:

Provide/Acquire: A.3.1.R Page 4 of5 SRO 3.7

1. Computer with access to Exam Reference Disk, or EIP 14.0, ver 22.0 and M-1.0, version 18.0.

2. Calculator

3. pens/pencils

4. Scrap paper Critical ELEMENT justification:

STEP Evaluation l.a CRITICAL - Task Objective l.b CRITICAL - Task Objective l.c CRITICAL - Task Objective 2 CRITICAL - Task Objective 3 CRITICAL - Task Objective COMMENTS:

FNP HLT-33 ADMIN A.3.1.R HANDOUT Page 1 of 1 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. 1A RHR pump is air bound and must be vented per AOP-12, Attachment 1, RHR Pump Venting. c. The TSC has requested that lB RHR pump motor bearing oil levels be checked and filled as required after restoring 1A RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 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: o Calculate the expected dose for tasks 1 through 3 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.

Task Time allowed! Dose Location/Task description reqd Rate Dose ff (minutes) (R!hr) 1 83 1A RHR Pump and HX rooms! Vent rig installation and 30 5 31 venting 2 too piping penetration room! Vent rig installation and 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 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 A.3.l.R HANDOUT Page 1 of 1 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. IA RHR pump is air bound and must be vented per AOP-I2, Attachment 1, RHR Pump Venting.

c. The TSC has requested that IB RHR pump motor bearing oil levels be checked and filled as required after restoring IA RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 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:

o Calculate the expected dose for tasks 1 through 3 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.

Task Location/Task description Time allowed/ req'd Dose Rate Dose 2 3 4 83' IA RHR Pump and HX rooms/ Vent rig installation and 121' piping penetration room/ Vent rig installation and Inspect IB RHR pump motor bearing oil levels and fill as 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 1 of 5 A.3.1.S Radiation Control ADMIN G2.3.9 SRO CRO-A.3. 1.S TITLE: Calculate the Maximum Permissible Stay Time within Emergency Dose Limits. PROGRAM APPLICABLE: SOT SOCT____ OLT X LOCT____ ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 20 MTN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL 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 1 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 1 through 3 Determine if a Repair team would exceed equipment protection emergency dose limits 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 E1 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary) EXAMINER: Developer Howard Fitzwater 1 1/06/09 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP HLT-33 ADMIN Page 1 of 5 A.3.1.S Radiation Control ADMIN G2.3.9 - SRO CRO-A.3.1.S TITLE: Calculate the Maximum Permissible Stay Time within Emergency Dose Limits. PROGRAM APPLICABLE: SOT SOCT OLT ~ LOCT __ ACCEPTABLE EVALUATION METHOD: ~PERFORM SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: NIA ALTERNATE PATH TIME CRITICAL 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 1 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 1 through 3 Determine if a Repair team would exceed equipment protection emergency dose limits ofEIP-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 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary) EXAMINER: ________________ __ Howard Fitzwater 11106/09 SEE NUREG 1021 FORM ES-301-3

FNP HLT-33 ADMIN A.3.1.S Page 2 of 5 CONDITIONS When I tell you to begin, you are to determine if exposure is within emergency dose limits of 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 1. b. 1A RHR pump is air bound and must be vented per AOP-12, Attachment 1, RHR Pump Venting. c. The TSC has requested that lB RHR pump motor bearing oil levels be checked and filled as required after restoring 1A RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 1 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 1 through 3 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.

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.

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. Task Time allowed! Dose Location/Task description reqd Rate I Dose (minutes) (RJhr) 1 83 1A RHR Pump and HX rooms/ Vent rig installation and 30 5 31 venting 2 too piping penetration room/ Vent rig installation and 15 19 75 venting 121 piping penetration room/ Vent rig installation and 20 5 65 venting INITIATING CUE: You may begin. FNP HL T -33 ADMIN A.3.l.S CONDITIONS Page 2 of 5 When I tell you to begin, you are to determine if exposure is within emergency dose limits of 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.

b. IA RHRpump is air bound and must be vented per AOP-12, Attachment 1, RHR Pump Venting.

c. The TSC has requested that 1 B RHR pump motor bearing oil levels be checked and filled as required after restoring lA RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 1 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:

Task o Calculate the expected dose for tasks 1 through 3 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.

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.

Location/Task description 83' lA RHR Pump and HX rooms/ Vent rig installation and Time allowed/ req'd Dose Rate Dose 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 may begin."

FNP HLT-33 ADMIN A.3.1.S Page 3 of 5 EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS: (CIRCLE) START TIME

c. Task #3 (20min)x 5.65R /hr x lhr

=.88REM 60min}

1) Calculates (in REM) a.

2.66 {Range 2.6 to 2.7} S / U c. 1.88 {1.8to 1.9} S/U 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. 2. Evaluates Team exposure within emergency

2) Circles YES on handout OR S / U limits of EIP-14.0 for completion of tasks 1 states that team can perform through 3.

tasks 1 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 1 through 3 1OREM (2.66 + 4.94 + 1.88)REM 0 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 1

hr V60min time is 4.5 mins (O.52Rem, II =4.493mm 7REMA hr ) ( {Range: 3 mm to 6 mm) RANGE :3mmnto6min 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.

1. Determine the dose received for tasks 1 through 3.

a. Task#1 (30min)x5.31R/hrxl lhr 1=2.66REM 60mmn)

b. Task #2 (l5min)x19.75R/hrxl lui 1 = 4.938REM 60 mm) b.

4.938 {4.9 to 5.0} S / U FNP HLT-33 ADMIN A.3.1.S EVALUATION CHECKLIST ELEMENTS: START TIME

1. Determine the dose received for tasks 1 through 3.

a. Task #1 (30min)x 5.31RI hr x ( 1hr. ) = 2.66REM 60mm

b. Task#2 (15min)x19.75Rlhrx( 1hr. )=4.938REM 60mm

c. Task#3 (20min)x 5.65RI hr x( 1hr. ) = 1.88REM 60mm STANDARDS:

1) Calculates (in REM)

a. 2.66

{Range 2.6 to 2.7}

b. 4.938 {4.9 to 5.0}

c. 1.88

{1.8 to 1.9} Page 3 of 5 RESULTS: (CIRCLE) S/U S I U S/U NOTE: A Cue may be required to obtain responses for each element if the candidate does not c1earl document results. Provide the Cue as stated on the Handout.

2. Evaluates Team exposure within emergency limits of EIP-14.0 for completion of tasks 1 through 3.

a.

Emergency Dose limit for equipment protection is 10 R and DOES NOT include current exposure.

b.

Summation of Task 1 through 3 1 OREM - (2.66 + 4.94 + 1.88 )REM ~ 0 0.52REM ~ 0

c.

Determines BOTH team members can complete all tasks.

3. Calculates stay time for task #4.

(0.52Rem{ hr )(60min) = 4.493 min \\ 7 REM hr {RANGE: 3 min_to _ 6min} STOP TIME

2) Circles YES on handout -OR-states that team can perform tasks 1 through 3.

a. 10 R is limit

b. 0.52 R remains available

c. Circles the YES choice

3) Documents or States: STAY time is 4.5 mins

{Range: 3 min to 6 min) Terminate when all elements of the task have been completed. S I U S/U CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNP HLT-33 ADMIN A.3.1.S Page 4 of 5 GENERAL

REFERENCES:

1. FNP-0-EIP-14.0, ver 22 2. FNP-0-M-1.0, ver 18.0 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. 2. Calculator 3. pens/pencils 4. Scrap paper Critical ELEMENT justification: STEP Evaluation l.a CRITICAL - Task Objective 1.b CRITICAL - Task Objective 1.c CRITICAL - Task Objective 2 CRITICAL - Task Objective 3 CRITICAL - Task Objective COMMENTS: IF Teds year to date dose is used, the emergency dose limit will be exceeded and the expected response for element 2 is NO and highest task that can be completed is Task #3. IF Joels year to date dose is used and the Emergency dose is reduced by this value then the stay time 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 5 REM then Task #2 will be the highest. FNP HLT-33 ADMIN GENERAL

REFERENCES:

1. FNP-0-EIP-14.0, ver 22

2. FNP-O-M-1.0, ver 18.0

3. KA: G2.3.4 RO 3.2 GENERAL TOOLS AND EQUIPMENT:

Provide/Acquire: A.3.1.S Page 4 of5 SRO 3.7

1. Computer with access to Exam Reference Disk, or EIP 14.0, ver 22.0 and M-1.0, version 18.0.

2. Calculator

3. pens/pencils

4. Scrap paper Critical ELEMENT justification:

STEP Evaluation 1.a CRITICAL - Task Objective 1.b CRITICAL - Task Objective I.c CRITICAL - Task Objective 2 CRITICAL - Task Objective 3 CRITICAL - Task Objective COMMENTS: IF Ted's year to date dose is used, the emergency dose limit will be exceeded and the expected response for element 2 is "NO" and highest task that can be completed is Task #3. IF Joel's year to date dose is used and the Emergency dose is reduced by this value then the stay time 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 5 REM then Task #2 will be the highest.

FNP HLT-33 ADMIN A.3.l.S HANDOUT Page 1 of I CONDITIONS When I tell you to begin, you are to determine if exposure is within emergency dose limits of 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 1. b. 1A RHR pump is air bound and must be vented per AOP-12, Attachment 1, RHR Pump Venting. c. The TSC has requested that lB RHR pump motor bearing oil levels be checked and filled as required after restoring 1A RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 1 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 1 through 3 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.

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.

Task Time allowed! Dose 44 Location/Task description reqd Rate (minutes) (RJhr) 1 83 1A R}{R Pump and HX rooms/ Vent rig installation and 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 Can this team perform all of the tasks? (Circle one) YES / NO IF yes, then state the maximum permitted stay time for task #4. Dose 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 7 IF no, then state the highest sequential task # that can be performed, if any. FNP HLT-33 ADMIN A.3.1.S HANDOUT Page 1 of 1 CONDITIONS When I tell you to begin, you are to determine if exposure is within emergency dose limits of 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 1.

b. 1A RHR pump is air bound and must be vented per AOP-12, Attachment 1, RHR Pump Venting.

c. The TSC has requested that 1 B RHR pump motor bearing oil levels be checked and filled as required after restoring 1A RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 1 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:

Task o Calculate the expected dose for tasks 1 through 3 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.

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.

Location/Task description 83' 1A RHR Pump and HX rooms/ Vent rig installation and Time allowed/ req'd Dose Rate Dose 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 Page 1 ofl3 A.4.l.A Emergency Plan G2.4.14 RO & SRO CRO-362 TITLE: Make Initial Notifications As Required for an Emergency PROGRAM APPLICABLE: SOT SOCT OLT X LOCT X ACCEPTABLE EVALUATION METHOD: X PERFORM X SIMULATE EVALUATION LOCATION: 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 1 handout then provide both EIP-9.0 Guideline 1 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 0 through step X. Examinee: Overall 3PM Performance: Satisfactory 1 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary) EXAMINER: Developer Howard Fitzwater 03/21/2010 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP HLT-33 ADMIN A.4.1.A Emer ency Plan G2.4.14 - RO & SRO CRO-362 TITLE: Make Initial Notifications As Required for an Emergency PROGRAM APPLICABLE: SOT SOCT OLT~LOCT~ ACCEPTABLE EVALUATION METHOD: ~ PERFORM ~ SIMULATE EVALUATION LOCATION: 2L Classroom PROJECTED TIME: 20 MIN TIME CRITICAL ~

THIS JPM IS TIME CRITICAL*

JPM DIRECTIONS: Page 1 of 13

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 1 handout then provide both EIP-9.0 Guideline 1 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 0 through step X. Examinee: Overall JPM Performance: Satisfactory 0 Unsatisfactory 0 Evaluator Comments (attach additional sheets if necessary) EXAMINER: _________ _ Howard Fitzwater 03/2112010 SEE NUREG 1021 FORM ES-301-3

FNP HLT-33 ADMIN A.4.1.A Page 2 of 13 CONDITIONS When I tell you to begin, you are to make initial notifications as required for an emergency and activate the emergency callout system. The conditions under which this task is to be performed are: a. A General Emergency has just been declared by the Shift Manager due to an event on Unit 1. b. The Shift Manager has handed you EIP-8.3, Table 2, and EIP-9.O, Guideline 1, GENERAL EMERGENCY RED INITIAL NOTIFICATION FORM. c. The Shift Manager has directed you to:

PERFORIvI the initial ENN notification over the 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. 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. LINE 12: Shutdown at Time TIME/DATE; use declaration time minus 10 minutes. LINE 17: APPROVAL 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 1 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 1 can be accomplished after the initial notification. FNP HL T-33 ADMIN AA.1.A Page 2 of 13 CONDITIONS When I tell you to begin, you are to make initial notifications as required for an emergency and activate the emergency callout system. The conditions under which this task is to be performed are:

a.

A General Emergency has just been declared by the Shift Manager due to an event on Unit 1.

b. The Shift Manager has handed you EIP-8.3, Table 2, and EIP-9.0, Guideline 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.

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" TIMEIDATE; use time at which the JPM is started. LINE 12: "Shutdown at Time" TIMEIDATE; use declaration time minus 10 minutes. LINE 17: "APPROVAL TimeIDATE"; use time at which the JPM is started. ALSO FILL IN AN APPROPRIATE TIME/DATE FOR AFFECTED UNIT SHUTDOWN. EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS: (CIRCLE) TIME CRITICAL ELEMENT and JPM START TIME UP TO 15 MINUTES NOTE: Element 1 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 1 can be accomplished after the initial notification.

FNP HLT-33 ADMIN A.4.1.A Page 3 of 13 EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS: (CIRCLE)

1.

Initiate the ERO callout system per EIP-8.3 Table 2 provided by the Shift Manager. prompts that the system would provide: Enter the scenario activation password, followed by the pound sign. you have entered (#entered). Is that correct? Enter 9 for yes, or 6 for no Enter the scenario activation number, followed by the pound sign. you have entered (#entered). Is that correct? Enter 9 for yes, or 6 for no press 3 to build the scenario the scenario is building

2.

Verify the Southern LINC ENN Radio being used is turned on From any plant telephone dial the number specified on the table to contact the ERO callout system. When prompted, the SCENARIO ACTIVATION PASSWORD (123456789) and the SCENARIO ID (87246) from EIP-8.3 Table 2 is entered. When directed the three (3) key is pushed. (Cue. The security tower called and indicated that their pager activated with 800-204-8196, and that the ERO callout system called and delivered message 3. Red light on power supply is lit and radio is actually turned on. S/U S/U S/U S/U CAUTION: Ensure that no actual transmissions to emergency agencies occur. o WIDE AREA, TRN ENN should be used in lieu of WIDE AREA, FEP ENN

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 is name/title at Farley Nuclear Plant. Please obtain a GENERAL EMERGENCY RED initial notification form and monitor the 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 HL T-33 ADMIN EVALUATION CHECKLIST A.4.1.A ELEMENTS:

1.

Initiate the ERO callout system per EIP-8.3 Table 2 provided by the Shift Manager. prompts that the system would provide: "Enter the scenario activation password, followed by the pound sign." "you have entered (#entered). Is that correct? Enter 9 for yes, or 6 for no" "Enter the scenario activation number, followed by the pound sign." "you have entered (#entered). Is that correct? Enter 9 for yes, or 6 for no" "press 3 to build the scenario" "the scenario is building"

2.

Verify the Southern LINC ENN Radio being used is turned on STANDARDS: From any plant telephone dial the number specified on the table to contact the ERO callout system. When prompted, the SCENARIO ACTIVATION PASSWORD (123456789) and the SCENARIO ID (87246) from EIP-8.3 Table 2 is entered. When directed the three (3) key is pushed. (Cue. "The security tower called and indicated that their pager activated with 800-204-8196, and that the ERO callout system called and delivered message 3". Red light on power supply is lit and radio is actually turned on. CAUTION: Ensure that no actual transmissions to emergency agencies occur. Page 3 of 13 RESULTS: (CIRCLE) S/U S / U S / U S/U o WIDE AREA, TRN ENN should be used in lieu of "WIDE AREA, FEP ENN"

3.

Initiate initial notifications using the Emergency Notification Network (ENN). Press group pushbutton, verify display shows WIDE AREA, TRN ENN. An Instructor will be on the other Southern LINC ENN Radio. See below for student announcement. S / U Press PTT, wait for the chirp and announce "This is name/title at Farley Nuclear Plant. Please obtain a GENERAL EMERGENCY RED initial notification form and monitor the 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 ADMIN A.4.1.A Page 4 of 13 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE)

4 Contact ONE Alabama State Agency.

Contact one of the Alabama State S I U Agencies listed on Guideline 1 form. When the candidate asks for the first state agency in each category the instructor will say the following: (CUE: Alabama Radiation Control at Montgomery EOC acknowledges manning the ENN). When asked, the INSTRUCTOR will say, John Brown is on the line.

5*

Contact ONE Georgia State Agency. Contact with the Georgia State S / U Agencies listed on Guideline I form is attempted until one agency acknowledges. (CUE: GEMA acknowledges manning the ENN, Ed Stern is on the line.)

6.

Contact Houston County. Contacts Houston County per S / U Guideline 1 form. (CUE: Houston County acknowledges manning the ENN, Steve Smith is on the line.).

7 Contact Early County.

Contacts Early County per S / U Guideline 1 form (CUE: Early County acknowledges manning the ENN, Chuck Tew is on the 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 I form. ATTEMPT was made. 9. Conduct pre-message announcement. Initial notification preparation S / U message is read per Guideline 1 form, step U. See below: Please prepare to receive a GENERAL EMERGENCY, RED initial notification message with acknowledgment

10.

Slowly read initial notification message Guideline 1 form read. The S / U over the ENN. following is the REQUIRED minimum information to be read. 1 A DRILL Message # 001 S / U 2 A INITIAL S/U 4 D General Emergency RG1 S / U 5 B Evacuate A B-5 C-5 J-5 S / U K-5 FNP HL T-33 ADMIN EVALUATION CHECKLIST ELEMENTS:

4.

Contact ONE Alabama State Agency. A.4.1.A STANDARDS: Contact one of the Alabama State Agencies listed on Guideline 1 form. When the candidate asks for the first state agency in each category the instructor will say the following: Page 4 of 13 RESULTS: (CIRCLE) S/U (CUE: "Alabama Radiation Control at Montgomery EOC acknowledges manning the ENN"). When asked, the INSTRUCTOR will say, "John Brown is on the line."

5.

Contact ONE Georgia State Agency. Contact with the Georgia State S I U Agencies listed on Guideline 1 form is attempted until one agency acknowledges. (CUE: "GEMA acknowledges manning the ENN, Ed Stern is on the line.")

6.

Contact Houston County. Contacts Houston County per Guideline 1 form. (CUE: "Houston County acknowledges manning the ENN, Steve Smith is on the line.").

7.

Contact Early County. Contacts Early County per Guideline 1 form (CUE: "Early County acknowledges manning the ENN, Chuck Tew is on the line.").

8.

Fill in the date and time on line 2 using the time that the first state agency contact A TTEMPT was made. The correct date and time are entered on the Guideline 1 form. S I U S/U S I U

9.

Conduct pre-message announcement. Initial notification preparation S I U message is read per Guideline 1 form, step U. See below: "Please prepare to receive a GENERAL EMERGENCY, RED initial notification message with acknowledgment"

1 O.

Slowly read initial notification message over the ENN. 1 A DRILL Message # 001 2 A INITIAL 4 D General Emergency RGI 5 B Evacuate A B-5 C-5 J-5 K-5 Guideline 1 form read. The following is the REQUIRED minimum information to be read. SIU S/U S/U S/U S/U

FNPHLT-33ADMIN A.4.1.A Page5ofl3 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) D Advise Remainder of EPZ to Monitor Local S / U Radio/TV Stations! TARs for Additional Information and CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POLICY. 6 B is Occurring S I U 7 C Above normal operating limits S / U 8 B Stable S/U 9 wind direction from 335 degrees S / U wind speed A mph precipitation none stability class E 10 A declaration time Date 5 / U Whatever is written 11 Affected unit(s) 1 S / U

12 and 13 is not r&iuired to be read 17 approved by W.T. DOOR, Emergency S / U Director, and read Time and Date

11.

Verify acknowledgment from Alabama Alabama Radiation Control at S / U Radiation Control at Montgomery EOC and Montgomery EOC and GEMA GEMA. questioned regarding receipt of initial notification message. (CUE: Alabama Radiation Control at Montgomery EOC and GEMA acknowledge receipt of initial 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 County acknowledge receipt of initial notification message). The below action is to be simulated only. 13. Fax a copy of the Guideline 1 form to the Guideline 1 form transmitted to S / U state of Florida. Florida using speed dial button number 10. (CUE: The fax machine sends the form to Florida). FNP HLT-33 ADMIN EVALUATION CHECKLIST AA.1.A Page 5 of 13 ELEMENTS: 6 7 8 9 10 11 D Advise Remainder ofEPZ 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. B is Occurring C Above normal operating limits B Stable wind direction from 335 degrees wind speed 3.4 mph precipitation none stability class ~ A declaration time Date --- Whatever is written Affected unite s) 1

12 and 13 is not required to be read 17

11.
12.

approved by W.T. DOOR, Emergency Director, and read Time and Date Verify acknowledgment from Alabama Radiation Control at Montgomery EOC and GEMA. Verify acknowledgment from Houston County and Early County The below action is to be simulated only.

13.

Fax a copy of the Guideline 1 form to the state of Florida. STANDARDS: RESULTS: (CIRCLE) S I U S I U S I U S I U S I U S I U S I U S I U Alabama Radiation Control at S I U Montgomery EOC and GEMA questioned regarding receipt of initial notification message. (CUE: "Alabama Radiation Control at Montgomery EOC and GEMA acknowledge receipt of initial notification message"). Houston County and Early County S I U questioned regarding receipt of initial notification message. (CUE: "Houston County and Early County acknowledge receipt of initial notification message"). Guideline 1 form transmitted to Florida using speed dial button number 10. (CUE: "The fax machine sends the form to Florida"). S I U

FNP HLT-33 ADMIN A.4.1.A Page 6 of 13 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 14. After receiving the fax report, Verify the Contacts the State of Florida to S / U state of Florida received the fax. confirm receipt of the Guideline 1 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 accomplished. CRITICAL ELEMENTS: Critical Elements are denoted with an Asterisk (*) preceding the element number. GENERAL

REFERENCES:

1. FNP-O-ETP-8.3 version 12 2. FNP-O-EIP-9.O Guideline 1, GENERAL EMERGENCY RED INITIAL NOTIFICATION FORM version 60 3. KAs: G2.4.43 RO-3.2 SRO-3.8 GENERAL TOOLS AND EQUIPMENT: None COMMENTS: FNP HL T-33 ADMIN EVALUATION CHECKLIST ELEMENTS:

14.

After receiving the fax report, Verify the state of Florida received the fax. STOP TIME A.4.1.A STANDARDS: Page 6 of 13 RESULTS: (CIRCLE) Contacts the State of Florida to S / U confirm receipt of the Guideline 1 form (CUE: Florida acknowledges receipt of the form). Terminate JPM when initial notification message is faxed to Florida and the ERO callout has been accom lished. CRITICAL ELEMENTS: Critical Elements are denoted with an Asterisk (*) preceding the element number. GENERAL

REFERENCES:

1.

FNP-0-EIP-8.3 version 12

2.

FNP-0-EIP-9.0 Guideline 1, GENERAL EMERGENCY RED INITIAL NOTIFICATION FORM version 60

3.

KAs: G2.4.43 RO-3.2 SRO-3.8 GENERAL TOOLS AND EQUIPMENT: None COMMENTS:

FNPHLT-33ADM(N A.4.1.A Page7ofl3 SOUTHERN LINC Phone talker communication GUIDE Give this to the Instructor performing phone talker duties

4 (CUE: Alabama Radiation Control at Montgomery EOC acknowledges manning the ENN).

When asked, the INSTRUCTOR will say, John Brown is on the line.

5 (CUE: GEMA acknowledges manning the ENN, Ed Stern is on the line.)
6 (CUE: Houston County acknowledges manning the ENN, Steve Smith is on the line.).
7 (CUE: Early County acknowledges manning the ENN, Chuck Tew is on the line.).
11 (CUE: Alabama Radiation Control at Montgomery EOC and GEMA acknowledge receipt of initial notification message).
12 (CUE: Houston County and Early County acknowledge receipt of initial notification message).
14 (CUE: Florida acknowledges receipt of the form).

FNP HLT-33 ADMIN AA.1.A Page 7 of 13 SOUTHERN LINC Phone talker communication GUIDE Give this to the Instructor performing phone talker duties

4 (CUE: "Alabama Radiation Control at Montgomery EOC acknowledges manning the ENN").

When asked, the INSTRUCTOR will say, "John Brown is on the line."

5 (CUE: "GEMA acknowledges manning the ENN, Ed Stern is on the line.")
6 (CUE: "Houston County acknowledges manning the ENN, Steve Smith is on the line.").
7 (CUE: "Early County acknowledges manning the ENN, Chuck Tew is on the line.").
11 (CUE: "Alabama Radiation Control at Montgomery EOC and GEMA acknowledge receipt of initial notification message").
12 (CUE: "Houston County and Early County acknowledge receipt of initial notification message").
14 (CUE: Florida acknowledges receipt of the form).

FNP HLT-33 ADMIN A.4.1.A Page 1 of 1 CONDITIONS When I tell you to begin, you are to make initial notifications as required for an emergency and activate the emergency callout system. The conditions under which this task is to be performed are: a. A General Emergency has just been declared by the Shift Manager due to an event on Unit 1. b. The Shift Manager has handed you EIP-8.3, Table 2, and EIP-9.O, Guideline 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.

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. FNP HL T-33 ADMIN AA.1.A CONDITIONS Page 1 of 1 When I tell you to begin, you are to make initial notifications as required for an emergency and activate the emergency callout system. The conditions under which this task is to be performed are:

a.

A General Emergency has just been declared by the Shift Manager due to an event on Unit 1.

b. The Shift Manager has handed you EIP-8.3, Table 2, and EIP-9.0, Guideline 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.

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 Table 2 INFORMATION FOR EMERGENCY RESPONSE NOTIFICATION SYSTEM ACTIVATION 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 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 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 1 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 (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 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-O-EI P-8. 3 Table 2 rNFORMA TION FOR EMERGENCY RESPONSE NOTIFICATION SYSTEM ACTIVATION

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 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: ___ 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 1 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) 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. 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 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 callout the emergency response staff. 11. Message Numbers Message 1 EMERGENCY CALL OUT 99911 Scenario Identification 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 Scenario Identification 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 not try to leave the plant or report to your emergency response facility. Follow the directions issued over the plant public address system. THIS IS NOT A DRILL Message 3 DRILL CALL OUT 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 Scenario Identification 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 2 of 2 Version 12 04/05/2010 05:30:00 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.

Ifboth systems have failed to activate, proceed to FNP-0-EIP-8.3, step 11, to manually callout the emergency response staff.

11.

Message Numbers Message 1 EMERGENCY CALL OUT 9 9 911 Scenario Identification 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: _________ _ 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 not try to leave the plant or repoli to your emergency response facility. Follow the directions issued over the plant public address system. THIS IS NOT A DRILL Message 3 DRILL CALL OUT Scenario Identification Number: 87246 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: _________ _ 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 2 of 2 Version 12

04/05/2010 05:30:00 FNP-0-EIP-9.0 GUIDELINE I GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM Mark box A if no emergency release is in progress or has occurred Mark box B if an emergency release is in progress Mark box C if an emergency release has occurred, but is currently stopped 1 DRILL JACTUAL EVENT 2 INITIAL

3. SITE: FARLEY NUCLEAR PLANT

4. EMERGENCY CLASS ION:

BASEDONEAL#__________

5. PROTECTIVE ACTION RECOMMENDATIONS:

MESSAGE NOTIFICATION: TIME DATE / / AUTHENTICATION#NIA (334) 814-4662, 814-4663 Confirmation Phone # (334) 794-0800, 899-5156 (ext 4662, 4663) VACUATE jj SHELTER OTHER (JJ)3ENERAL EMERGENCY LC

6. EMERGENCY RELEASE:

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. None Occurring Has Occurred

7. RELEASE SIGNIFICANCE:

Not applicable Within normal bove normal J Under operating limits operating limits evaluation

8. EVENT PROGNOSIS:

j Improving tabIe Degrading

9. METEOROLOGICAL DATA:

Wind Direction from.degrees Wind Speed _ 4 mph 35 foot elevation preferred Precipitation Sbility Class j L1 EJ 1 D El 10 ECLARATION Time Date I /

11. AFFECTED UNIT(S):

12. UNIT STATUS:

Ui Power Shutdown at Time declaration time minus 10 minutes Date (Unaffected Unit(s) Status Not Required for

Initial Notifications) U2 Power Shutdown at Time Date /I

13. REMARKS:

No additional remarks read additional remarks on separate page

17. APPROVED BY:

07, 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._Line I check box A or B. Select B only if it is an actual event in the plant B. Line 1 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 right method of evaluation. For example, if site criteria is met for EAL 5A5 and FAlsimultaneously, FA1 should be listed on line 4. E.Line 5 Refer to NMP-EP-109, Protective Action Recommendations to determine appropriate Protective Action Recommendations (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. 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 29B(NG) 6 OF 8 Version 60.0 04/05/2010 05:30:00 I§] ACTUAL EVENT GUIDELINE 1 GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM FNP-0-EIP-9.0 MESSAGE /JOI 1DRILL 2@INITIAL NOTIFICATION: TIME _____ DATE_-'-_-'--_.AUTHENTICATION # N/A

3. SITE: FARLEY NUCLEAR PLANT

4. EMERGENCY CLASS~ION:

BASED ON EAL # t{l.;il

5. PROTECTIVE ACTION RECOMMENDATIONS:

@=VACUATE 19 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 _____________________ ~~

6. EMERGENCY RELEASE:

~ None

7. RELEASE SIGNIFICANCE:

~ Not applicable I§] Within normal operating limits 19 Has Occurred C bove normal operating limits IQ] Under evaluation

8. EVENT PROGNOSIS:

~ Improving @>table

9. METEOROLOGICAL DATA:

Wind Direction from 335degreeS 35 foot elevation preferred Precipitation I<<J#ee 19 Degrading Wind Speed 3. 4mPh Stability Class §I @I 19 [Q] 1 O~ECLARATION Time ____________ Date __

11. AFFECTED UNIT(S): @ []

16m

12. UNIT STATUS:

(Unaffected Unites) Status Not Required for Initial Notifications) ~ U1 __ % Power Shutdown at Time declaration time minus 10 minutes Date Today @I U2 __ % Power Shutdown at Time __________ Date _, ___, __ _

13. REMARKS:

No additional remarks D read additional remarks on separate page

17. APPROVED BY:

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 I check box A or B. Select B only if it is an actual event in the plant B.-*Line I 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 right method of evaluation. For example, ifsite criteria is met for EAL SA5 and FAlsimultaneously, FAI should be listed on line 4. E.-><-Line 5 Refer to NMP-EP-I09, Protective Action Recommendations to determine appropriate Protective Action Recommendations (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-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-29B(NG) Mark box A if no emergency release is in progress or has occurred Mark box B if an emergency release is in progress Mark box C if an emergency release has occurred, but is currently stopped 6 OF 8 Version 60.0

04/05/2010 05:30:00 FNP-0-EIP-9.0 GUIDELINE I GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM G.Line 7 Release Significance. Mark box A, B, C or D. Normal limits are being exceeded if an effluent monitor listed in step F above is in alarm Mark box A if 6A is marked Mark box B if 6B or 6C is marked and NO effluent monitor is or has been in alarm. Mark box C if 6B or 6C is marked and ANY effluent monitor is or has been in alarm. Mark box D if 6B or 6C is marked and it can not be determined if an effluent monitor is or has been in alarm. H.Line 8 Event Prognosis. Mark box A, B or C. A should be marked if mitigation efforts appear successful, progressing toward termination/recovery. B should be marked if escalation to a higher classification is unlikely based on current conditions. C should be marked if escalation to a higher emergency classification or PAR change is likely. I. >< Line 9 Meteorological Data Fill in the meteorological data required (35 foot elevation preferred). When possible use 15 minute average data, available from EP_WEATHER on the IPC. If EP WEATHER. Is not available then use the guidance in FNP-0-EIP-9.3 Data Sheet I for obtaining meteorological data. If stability class is not available it can be calculated from delta temperature from the below table AT (200 elev. temp, °F - 35 elev. temp, °F) Stability Class <-1.74 A -1.74 to <-1.56 B -1.56 to <-1.38 C -1.38 to <-0.46 D -0.46 to<1.38 E 1.38 to 3.60 F >3.60 G J. Line 10 Time is for the declaration checked in line 4 K<Line 11 Mark the unit that is involved with the emergency declaration, or all if both units are affected. L.Line 12 Fill in the per cent power or the time of shutdown for units involved with the event MLine 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. The Emergency Director must sign the form with time and date. 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. If the Southern LINC display does not show WIDE AREA, FEP 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 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 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 is name/title at Farley Nuclear Plant. Please obtain a GENERAL EMERGENCY RED initial notification form and monitor the 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 ifthey 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. 205-280-2310) Alabama Radiation Control at Alabama Forward EOC, ENN (1307), OPX 6621), (334-793-1565) HOUSTON COUNTY ENN (1307). OPX (6621), (334-794-9720, 793-9655, 677-4807. 4808) Time Name Acknowledged 04/05/2010 05:30:00 GUIDELINE 1 GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM FNP-0-EIP-9.0 G.~Line 7 Release Significance. Mark box A, B, C or D. Normal limits are being exceeded if an effluent monitor listed in step F above is in alarm Mark box A if 6A is marked Mark box B if 6B or 6C is marked and NO effluent monitor is or has been in alarm. Mark box C if 6B or 6C is marked and ANY effluent monitor is or has been in alarm. Mark box D if 6B or 6C is marked and it can not be determined if an effluent monitor is or has been in alarm. H.X-Line 8 Event Prognosis. Mark box A, B or C. A should be marked if mitigation efforts appear successful, progressing toward termination/recovery. B should be marked if escalation to a higher classification is unlikely based on current conditions. ". C should be marked if escalation to a higher emergency classification or PAR change is likely. L_" __ Line 9 Meteorological Data Fill in the meteorological data required (35 foot elevation preferred). When possible use 15 minute average data, available from EP _ WEATHER on the IPC. IfEP _ WEATHER. Is not available then use the guidance in FNP-O-EIP-9.3 Data Sheet I for obtaining meteorological data. If stability class is not available it can be calculated from delta temperature from the below table ~T (200' elev. temp, OF - 35' elev. temp, OF) Stability Class <-1.74 A -1.74 to <-1.56 B -1.56 to <-1.38 C -l.38 to <-0.46 D -0.46 to < l.38 E l.38 to 3.60 F >3.60 G J. >< Line 10 Time is for the declaration checked in line 4 K. ~Line 11 Mark the unit that is involved with the emergency declaration, or all if both units are affected. L. Line 12 Fill in the per cent power or the time of shutdown for units involved with the event M.>< 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._" __ The Emergency Director must sign the form with time and date. O. 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. __ Ifthe Southern LINC display does not show "WIDE AREA, FEP 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 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 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 is name/title at Farley Nuclear Plant. Please obtain a GENERAL EMERGENCY RED initial notification form and monitor the 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, 205-280-2310) Alabama Radiation Control at Alabama Forward EOC, ENN (1307), OPX 6621), (334-793-1565) HOUSTON COUNTY ENN (1307), OPX (6621), (334-794-9720, 793-9655, 677-4807, 4808) Time _____ Name __________.Acknowledged

04/05/2010 05:30:00 FNP-0-EIP-9.0 GUIDELINE I GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM Indicate the time of initial attempt to contact any Georgia agency. Circle agency actually contacted. Indicate the name of the individual contacted. Underlined phone numbers staffed 24 hours a day PTT and request one Georgia agency in the order listed below acknowledge manning of the ENN. State agency name and ask ifthey are on the line. Release the PTT after each request. GEORGIA State Agencies In preferred order GEMA at Atlanta EOC, ENN (1304), OPX (6629). (404-635-7200) GEMA at Georgia Forward EOC, ENN (1308) OPX (6626), (229-723-4826) EARLY COUNTY, ENN(1308) OPX (6622),(229-723-3577, 3578, 4826) Time Name Acknowledged LI 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 they are on the line. Release the PTT after each request. HOUSTON COUNTY HOUSTON COUNTY, ENN(1307), OPX (6621), (334-794-9720, 793-9655, 334-677-4807, 4808) Time Name Acknowledged LI Indicate the time of initial attempt to contact Early County. Indicate the name ofthe 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(1308) OPX (6622), (229-723-3577, 3578, 4826) Time Name Acknowledged LI 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 prepare to receive a GENERAL EMERGENCY, RED initial notification message with 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 FNP-0-EIP-8. 1 to contact them by any available means as soon as possible. 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 verif, the state of Florida has received the Fax by calling. (800-320-0519) (850-413-9911) 8 OF 8 Version 60.0 04/05/2010 05:30:00 GUIDELINE 1 GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM FNP-0-EIP-9.0 Indicate the time of initial attempt to contact any Georgia agency. Circle agency actually contacted. Indicate the name ofthe individual contacted. Underlined phone numbers staffed 24 hours a day PTT and request one Georgia 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. GEORGIA State Agencies In preferred order GEM A at Atlanta EOC, ENN (1304), OPX (6629), (404-635-7200) GEMA at Georgia Forward EOC, ENN (1308) OPX (6626), (229-723-4826) EARLY COUNTY, ENN(1308) OPX (6622),(229-723-3577, 3578, 4826) Time ____ Name __________ Acknowledged 0 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 ofthe ENN. State agency name and ask ifthey are on the line. Release the PTT after each request. HOUSTON COUNTY HOUSTON COUNTY, ENN(l307), OPX (6621), (334-794-9720, 793-9655, 334-677-4807, 4808) Time ____ Name __________ Acknowledged 0 Indicate the time of initial attempt to contact Early County. Indicate the name ofthe 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) OPX (6622), (229-723-3577, 3578, 4826) Time ____ Name, __________ Acknowledged 0 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 prepare to receive a GENERAL EMERGENCY, RED initial notification message with 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 FNP-0-EIP-8.1 to contact them by any available means as soon as possible. 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 the state of Florida has received the Fax by calling. (800-320-0519) (850-413-9911) 8 OF 8 Version 60.0}}

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ML101650639

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