ML101650280

Initial Exam 2010-301 Draft Administrative JPMs (Section 6)

ML101650280
Person / Time
Site:	Farley
Issue date:	06/07/2010
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
50-348/10-301, 50-364/10-301
Download: ML101650280 (97)

Text

ES-301 ES-301 Administrative Topics Outline Administrative Topics Outline Form Form ES-301-1 ES-SO 1-1 OPERATING OUTLINE OPERATING OUTLINE SUBMITTAL SUBMITTAL Facility: Farle~

Facility: Plant Nuclear Plant Farley Nuclear Date of Date of Examination:

Examination: March 8, 2010 March 8,2010 Examination Level:

Examination SRO ++ RO Level: SRO RO Operating Test Operating Number: FA2010301 Test Number: FA2010301 Administrative Topic Type

• TYJ!e Describe activity Describe activity to be be performed performed Code Co e*

(see Note)

Verification of Initial Initial Conditions Prior to Core Conditions Prior Core Alterations.

• plant conditions with fuel movement Given a set of plant movement in in A1.1.A progress, determine if all Core Alterations initial progress, initial Conduct of Operations N R N/R conditions are satisfied using UOP-4.1.

pOrtlOfl RO portion G2.l.40 (2.8/3.9)

G2.1.40 G2.1.36 (3.0/4.1)

G2.1.32 (3.8/4.0)

Verification of Initial Conditions Prior to Core Alterations.

Given a set of plant conditions with fuel movement in progress, determine if all Core Alterations initial Al. I .A A1.1.A conditions are satisfied using UOP-4.1, and then list all Conduct of Operations N/R N/R SRO portion Tech Spec conditions, REQUIRED ACTIONS and COMPLETION TIMES for LCOs not met.

G2.l.40 (2.8/3.9)

G2.1.40 G2.1.36 (3.0/4.1)

G2.2.1.35 (2.2/3.9) G2.1.32 (3.8/4.0)

G2.2.1.3S{2.2/3.9)

Al .2.S A1.2.S D/R D/R Conduct A Safety Shutdown Assessment and Determine Conduct of Operations Time to Saturation.

SRO ONLY G2.1.25 (3.9/4.2)

G2.1.2S A2.1.A Perform a Shutdown Margin Calculation in modes 1 1 &2 Equipment Control DIR D/R for a stuck rod (STP-29.S)

(STP-29.5)

SRO +RO+ RO (3.5/4.1) APEOOS 001A4.11 (3.S/4.1) APEOO5 AK1.0S AKI.05 (3.3/4.1)

A3. 1 .A A3.1.A M/R M/R Calculate the Maximum Permissible Stay Time within Radiation Control Emergency Dose Limits.

SRO + RO SRO+RO G2.3.4 (3.2/3.7)

A4. I .A A4.1.A MIS M/S Monitor the Critical Safety Function Status Trees Emergency Plan - manually (CSF-0.0)

(CSF-O.O)

SRO SRO+RO + RO G2.4.14 (3.8/4.5)

(3.8/4.S) G2.4.21 (SRO 4.0/4.6)

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (. <:5. 3 for ROs; ~ 4 for SROs & RO retakes) [112] [1/2]

(N)ew or (M)odified from bank (> 1) e 1) [313]

[3/3]

(P)revious 2 exams exams ( (~ I; 1; randomly selected) [010]

[0/0]

Farley Farley OCT OCT 2010 2010 NRC NRC ADMINADMIN exam exam outline outline Page Page 11 of of 11

ES-301 ES-301 Administrative Topics Administrative Topics Outline Outline Form Form ES-301-1 ES-301-1 OPERATING OUTLINE OPERATING OUTLINE SUBMITTAL SUBMITTAL Facility: Farley Facility: Nuclear Plant Farley Nuclear Plant Date of Date of Examination:

Examination:

Examination Level:

Examination Level: SRO SRO ++ RO RO Operating Test Operating Test Number:

Number: FA2010301 FA2010301 Administrative Topic Administrative Topic Type JY$e Describe activity Describe activity to to be be performed performed 0 e*

Code Note)

(see Note)

(see Verification of Verification Initial Conditions of Initial Conditions Prior Prior to to Core Core Alterations.

Alterations.

Given aa set Given set of plant conditions of plant conditions with with fuel fuel movement movement in in progress, determine progress, determine ifif refueling refueling operations operations can can continue, continue, and ifif not, and not, the the reason(s) reason(s) that prohibit refueling that prohibit refueling fromfrom continuing. UOP-4.1 continuing. UOP-4.1 P&Ls P&Ls andand TSTS and and TRM TRM requirements.

requirements.

A1.1.A A1.1.A G2.140 (2.8/3.9)

G2.1.40 (2.8/3.9) G2.1.36 (3.0/4.1)

G2.1.36 (3.0/4.1)

Conduct of Operations N/R N/R G2.1 .32 (3.8/4.0)

G2.1.32 POI RO portion Perform UOP-4.1 Perform UOP-4.1 appendix appendix 66 and and determine determine ifif all all core core alteration initial alteration initial conditions conditions areare satisfied.

satisfied. This This will will be done in be done in the classroom and we will use pictures of the Nt's the classroom Nis and radiation monitors that will show that one NI is not working and the audio count rate selector switch is selected to that NI. Also with fuel movement in the SFP SEP there will be one radiation monitor that is inoperable due to it being in test.

Verification of Initial Conditions Prior to Core Alterations.

Given a set of plant conditions with fuel movement in progress, determine if all Core Alterations initial conditions are satisfied using UOP-4.1, UOP-4. 1, and then list all Al .1 .A A1.1.A Tech Spec conditions, REQUIRED ACTIONS and Conduct of Operations NIR N/R COMPLETION TIMES for LCOs not met.

COMPLETION SRO portion G2.1.40 (2.8/3.9) G2.1.36 (3.0/4.1)

(3.014.1)

G2.2.1.35 G2.2.l.35 (2.2/3.9) G2.l.32 (3.8/4.0)

G2.1.32 This is the same JPM as above with the requirement to evaluate Tech Specs and TRM requirements that cover the conditions given and the REQUIRED ACTIONS and COMPLETION_TIMES_of COMPLETION TIMES of TS_3.9.2_and_TRM_13.3.4.

TS 3.9.2 and TRM 13.3.4.

Al .2.S A1.2.S D/R D /R Conduct A A Safety Shutdown Assessment and Determine Conduct of Operations Time to Saturation.

SRO ONLY G2.l.25 G2.1.25 (3.9/4.2)

This This JPM JPM will havehave thethe candidate candidate evaluate plant conditions, conditions, use aa table use table toto determine determine time to boiling and and then then fill out out UOP UOP-4.0, 4.0, figure la1a Core Core Cooling Cooling section section only.

only. This This isis only only performed performed by the SRO by the SRO job job function at Farley Farley Nuclear Nuclear Plant.

Plant.

A2.l A2.1.A.A Perform Perform aa Shutdown Shutdown MarginMargin Calculation Calculation in in modes modes 11 & & 22 Equipment Equipment Control Control for aa stuck stuck rod rod (STP-29.5)

(STP-29.5)

SRO ++RO RO D /R 001A4.111 (3.5/4.1) APEOO5 001A4.l APE005 AKi AK1.05.05 (3.3/4.1)

D/R One One Bank Bank DD rod rod isis 30 30 steps steps below below the the other other seven seven Bank Bank DD rods.

rods.

Determine Determine the the SDM SDM and and that that an an emergency emergency boration boration is_required.

is required.

Farley Farley OCT OCT 2010 2010 NRC NRC ADMIN ADMIN exam exam outline outline Page Page 11 of2 of2

ES-301 ES-301 Administrative Topics Outline Form ES-301-1 ES-301 -1 OPERATING OUTLINE SUBMITTAL A3.1 .A A3.1.A MIR MIR Calculate the Maximum Permissible Stay Time within Radiation Control Emergency Dose limits.Limits.

SRO +RO+ RO This JPM hashas the candidate assess a job where two workers be assigned a task during an emergency event to save a will be piece of equipment. There will be three stages to the valuable piece task in which the dose rate is given and time required to complete the task is given. The year to date dose rates will be given and the task will be to determine if either of the workers will exceed their dose limits of EIP-14. Information required to be known is that EDLs do not take into account current dose, admin limits and NRC limits do not apply and the EIP-14 limits must be applied properly.

G2.3.4 (3.2/3.7)

(3.2/3.7)

A4.1 .A A4.1.A MIS MIS Monitor the Critical Safety Function Status Trees Emergency Plan - (CSF-0.0) manually (CSF-O.O)

+ RO SRO +RO G2.4.14 (3.8/4.5) G2.4.21 (SRO 4.0/4.6)

The simulator will be used requiring the candidate to determine the appropriate CSF that applies. We have a snap setup that has N-42 failed high which will cause evaluation of FRP-S, to show a yellow path on FRP-C and H, an Orange path on FRP- FRP P and Z. A manual determination of CSF-O will be required as to which FRP is applicable based on the setup.

The RO will identify all the CSFs that are challenged and the SRO will have to use the procedures to determine which procedure is required due to the plant conditions.

• • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ~ ( 3 for ROs; ~< 4 for SROs & RO retakes) [1/2] [112]

(N)ew or (M)odified e (M)odifled from bank ( 1) [313]

[3I3]

(P)revious 2 exams << ( 1; randomly selected) [010] [OlO]

Changes since the draft submittal:

A1.1.A We could not find procedural guidance for the RHR flow requirement so a radiation monitor for the procedure being used was substituted for the RHR flow. Changed the appropriate Tech Spec to TRM 13.3.4 to adjust for the radiation monitor Inoperable.

A3.1.A added the KA value to ES-301-1 G2.3.4 (3.2/3.7)

A4.1.A We could not get the submitted simulator results fo having FRP-P.1 a red path, but we developed one with an Orange path. We also put in a failed NI into the scenario that will have FRP-S evaluated since one NI is >5% power, but failed, so it is not relevant.

Farley OCT 2010 NRC ADMIN exam outline Page 2 of 2 of2

HLT-33 FNP HL T-33 ADMIN Page 11 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 OL T -.-lL X LOCT 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 CRITICAL TIME CRITI CAL PRA __

PRA____

JPM DIRECTIONS:

1. This task is to be administered in a group, classroom setting with access to a variety of procedures (UOPs, (UOP5, 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:

• UOP-4. 1, Appendix 6, Verification OfInitial Evaluates all steps of UOP-4.1, Of Initial Conditions Prior To Core Alterations.

• Identifies all inoperable equipment or unsatisfied conditions that prevent completing the attachment, if any.

• (For SRO ONLY):

o Based on the conditions identified List all TS CONDITIONS, REQUIRED ACTIONS and COMPLETION TIMES for LCOs not met.

Examinee:

Overall JPM Performance: Satisfactory 0 Unsatisfactory U nsatisfactorv 0D Evaluator Comments (attach additional sheets if necessary)

EXAMINER: _________________

Developer H. Fitzwater 10/26/09 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNPHLT-33ADMIN FNP HLT-33 ADMIN A.1.1.A Page 2 of 10 Page2oflO CONDITIONS When I tell you to begin, you are to perform or evaluate all steps steps FNP-I-UOP-4.1, 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 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> 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. chemistrys request.

Rx Makeup water is being used to dilute the Reactor Cavity by chemistry's

h. FNP-1-STP-18.4, Containment Midloop and/or Refueling Integrity Verification and FNP-I-STP-18.4, Containment Closure, was completed yesterday at 1400.

i.

I. CTMT Main Purge system is in operation.

j.

J. The equipment hatch and all containment air locks are currently closed.

k. Applicable equipment can be assessed using the provided photographs.

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

You have been directed to perform or evaluate all steps of FNP-I-UOP-4.1,

m. Determine whether or not all Core Alterations initial conditions are satisfied.

INITIATING CUE: "You You may begin."

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 / UU 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 SS / U U

the Reactor Cavity verified within one hour. completed. Utilizes initial conditions to verify task complete.

NOTE:

NOTE:** Elements 33 through 5, 5, 77 and 88 are performed 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 standards column for the applicable light or switch).

switch).

FNP HL FNP HLT-33 ADMIN T-33 ADMIN A.1.1.A A.1.1.A Page Page 33 of of 10 10 EVALUATION CHECKLIST EVALUATION CHECKLIST RESULTS:

RESULTS:

ELEMENTS:

ELEMENTS: STANDARDS:

STANDARDS: (CIRCLE)

(CIRCLE)

Verify N-31, 3.2.1) VerifY

3. (STEP 3.2.1) N-3 1, Source Source Range NI, 3)

3) Determines step step 3.2.1 3.2.1 has been SS/U

/ U detector operable. Utilizes picture ofN-satisfied; Utilizes of N-determines that the 31 and determines the instrument isis operable.

instrument operable.

(reference SOP-39.0 (reference SOP-39.O section section 4.1)

N-3 I Instrument power on AND control

a. Check N-31 a. lights are illuminated power on lights illuminated.

b. Check switches aligned: b. Switches are in position:

i. Level Trip i. Normal I.

ii.Operation Selector ii. Normal iii.High Flux at shutdown iii. Normal

c. Perform a channel check per STP-1.0 STP-l .0 (SR c. Acceptable per STP-1.0 STP-I .0 3.9.2.1). allowances

• • 3.2.2) Verify N-32, Source Range NI,

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

(reference SOP-39.0 section 4.1)

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

• Control power light is NOT illuminated.

• • Instrument power is illuminated.

b. Check switches aligned: b. Switches are determined;

i. Level Trip i.I. Normal ii.Operation Selector II. Normal ii.

iii.High Flux at shutdown Ill. Normal iii.

c. Performs a channel check per STP-l .0 (SR STP-1.0 c. Acceptable per STP- STP-1.0 1 .0 3.9.2.1).

3.9.2.1). allowances.

FNP HLT-33 FNP HLT-33 ADMIN A.1 .1 .A A.1.1.A Page 4 of Page of 10 10 EVALUATION CHECKLIST CHECKLIST RESULTS:

ELEMENTS: STANDARDS:

STANDARDS: (CIRCLE)

(CIRCLE) 3.2.3) Verify N-48, Gamma-metrics

5. (STEP 3.2.3)Verify Gamma.metrics 5) Determines step 3.2.3 has been S / U Source Range NI, detector operable. satisfied. (May identify that the SOP-39.O section 4.3)

(reference SOP-39.0 Refueling Coordinator must first be consulted.)

a. Checks N-48 in service.

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

STP-1 .0 (SR

b. Performs a channel check per STP-I.O STP-1 .0

b. Acceptable per STP-I.O 3.9.2.1). Table 1I allowances.

6. (STEP 3.3) Reactor Coolant system 2000 ppm. 6) Determines step 3.3 has been S / U satisfied; Utilizes initial conditions to verify boron concentration.

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 The SS acknowledges the issue you have identified and directs you to continue. No compensatory actions have yet been completed."

completed.

• • 7. (STEP 3.4.1) Verifies R-5 operable/operating. 7) Identifies R-5 is NOT S / U operable/operating; Determines step 3.4.1 has NOT been satisfied. (May annotate failure

(

Reference:

SOP-45.0 section 4.1.3; TRM 13.3.4) 13.3.4) or need to initiate survey).

a. Verify Operation Selector switch position. a. Level Cal.

b. Verify Range Selector switch position. b. WIDE

c. Verify Drawer indication lights: c. Lights are:

i.I. Power i.l. ON ii.

11. Channel Test light ii. ON iii. High Alarm iii.

Ill. OFF iv.

IV. Low Alarm iv.

IV. OFF

FNP HL HLT-33 T-33 ADMIN A.1.1.A Page 5 of 10 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. i. Oper I.

ii. Pump Power Il. ii. ON 11.

iii. Pump Start iii. StartlN Ill. Start/Neutral eutral

d. Verify MCR lights: d. MCR lights are:

i. Power light I. i. ON I.

ii.

Il. Pump ON light ii. ON Il.

iii. Flow fault light iii. OFF Ill.

iv. Alert light IV. iv. OFF IV.

v. High light v. OFF vi. Fail/Reset light VI. vi. ON VI.

vii. Power on light vii. ON

9. (STEP 3.5 through 3.6) Evaluates Refueling 9) Utilizes initial conditions and SS / U U

integrity has been verified within 100 hrs, and evaluates that step 3.5 is that step 3.6 is not applicable, applicable. satisfied and 3.6 in N/A.

NOTE: REVIEW of completed Appendix 66 to evaluate the above elements.

CUE: Are core alterations initial conditions satisfied?

• • 10.Reports/annotates

10. Reports/annotates that step 3.2.2 and 3.4.1 are not 10) Identifies N32 inoperable, R- S U S / U completed or satisfied and that core Alts should 55 inoperable and that Core not be started. alterations should not be permitted since the initial conditions have not been satisfied.

FNPHLT-33ADMIN FNP HLT-33 ADMIN A.1.1.A A.1.1.A Page 6 of 10 Page6oflo EVALUATION CHECKLIST EVALUATION CHECKLIST RESULTS:

RESULTS:

ELEMENTS:

ELEMENTS: STANDARDS:

STANDARDS: (CIRCLE)

(CIRCLE)

RO ONLY:

RO ONLY: Terminate when Terminate when elements 1-10 of elements 1-10 of the the task task have have been been completed.

completed.

SRO ONLY SRO ONLY Cue: Cue: PROVIDE PROVIDE Handout Handout #2,#2, read read and and escort escort back back to to classroom classroom to to allow allow TS TS review.

review.

Based on Based on the the conditions conditions you you identified identified perform perform the the following:

following:

1) List

1) List all TS TS CONDITIONS, CONDITIONS, REQUIRED REQUIRED ACTIONS and COMPLETION TIMES for LCOs LCOs not met, if any.

• • 11. Evaluates TS 3.9.2 Condition C: Inoperable

11. II) Identifies the need to

11) S I/ U U

Audio Counts. IMMEDIATELY verify un- un borated water sources are isolated.

• • 12. Evaluates TRM 13.3.4 condition B.

12. 12) Identifies the need to

12) S I U IMMEDIATELY notify HP to perform survey the SFP area within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

NOTE: ** TS 3.9.2 Condition A is not required to be entered due to Gamma Metrics (as allowed by BASIS) and N-31 are OPERABLE. CONDITION A may be implemented and does not challenge personnel safety, equipment or license requirements.

However, IF CONDITION A is implemented, THEN element 13 is critical.

SEE 13. IF TS 3.9.2 implemented, THEN evaluates 13) Identifies the need to S I/ U S U NOTE TS 3.9.2 CONDITION A: One source range IMMEDIATELY Suspend neutron flux monitor inoperable. CORE ALTERATIONS AND positive reactivity additions (secure Reactor Cavity Makeup).

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.I, VER

1. UOP-4.1, VER 51 51 2.KA:#G2.1.40

2. KA: # G2.1.40 2.8 2.8 3.9 3.9 G2.1.36 G2.1.36 3.0 3.0 4.1 4.1 G2.1.32 G2.I.32 3.8 3.8 4.0 4.0

FNP HL FNP HLT-33 ADMIN T-33 ADMIN A.1.1.A A.1.1.A Page Page 77 of of 10 10 GENERAL TOOLS GENERAL TOOLS AND EQUIPMENT:

AND EQUIPMENT:

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

disk/files only.

2. Provide UOP-4.1,

2. UOP-4. 1, Appendix 66

3. Pen/pencil 3.

4. Pictures of

4. Pictures of the the following following components:

components: (11 (II pages pages total)

a. R-24A

a. R-24A Local Local indications indications g. R24A &

g. R24A & R25A R25A MCRMCR indications indications

b. R-24B Local indications h. R-24B & & R25B MCR indications indications

c. R-25A Local indications i.i. R-35A & & R35B MCR indications

d. R-25B Local indications j. N31 J. N3 drawer indications

e. R-35A Local indications k. N32 drawer indications

f. R-35B Local indications l.I. N3I, N3 1, N32 && N48 Board indications

m. Audio Count Rate Channel Drawer Critical ELEMENT justification:

STEP Evaluation NOTE: (a.b.c...)

The listed sub-steps to each element (a.b.c ... ) describe the anticipated actions taken by the substeps 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. critical--this step is for satisfying site procedural protocol and expectations.

NOT critical-this

2. NOT critical-critical this step is for satisfying site level expectations or requirements.

3. NOT critical-Although criticalAlthough Task objective-component is operable.

4. Critical Element -Task Task objective-evaluate operability of required equipment.

5. NOT criticalAlthough critical-Although Task objective-component is operable.

6. NOT critical - this step does not require any evaluation from the candidate.

7. Critical Element Task-Task objective-evaluate operability of required equipment.

8. NOT critical-Although criticalAlthough Task objective-components are operable.

9. Critical ElementFINAL Element-FINAL Task objective-identifies that initial conditions are not satisfied for Core Alts.

10.

10. NOT critical critical- this step does not require any evaluation from the candidate.

SRO Critical ElementIDENTIFIES Element-IDENTIFIES and IMPLEMENTS the Actions for License 11 II requirement.

SRO Critical Critical ElementIDENTIFIES Element-IDENTIFIES and IMPLEMENTS the Actions for License 12 12 requirement.

SRO Conditional Critical Critical ElementIDENTIFIES Element-IDENTIFIES and IMPLEMENTS the Actions for 13 13 License requirement.

IF the candidate implements this TS condition, then the actions must also be initiated initiated toto comply comply with with License requirements.

requirements.

FNP HL FNP HLT-33 ADMIN T-33 ADMIN A.1 .1 .A A.1.1.A Page Page 22 of of 10 10 COMMENTS:

COMMENTS:

References expected References expected to to be be utilized:

utilized:

STP-1 .0 Table STP-1.0 Table 11 and and Appendix Appendix 3, 3, Ver.

Ver. 97.0; 97.0; channel channel check check information information M-50 Master M-50 Master list list of Surveillance Tests, of Surveillance Tests, Ver.

Ver. 25.0; determine channel 25.0; determine channel check check procedure procedure SOP-3 9.0, Nuclear SOP-39.0, Nuclear Instrumentation Instrumentation System, System, Ver.

Ver. 9.0; evaluate switch 9.0; evaluate switch alignment/operability alignment/operability SOP-45.0, Radiation SOP-45.0, Radiation Monitoring Monitoring System, System, Ver.

Ver. 35.0; evaluate switch 35.0; evaluate switch alignment/operability alignment/operability TRM 13.3.4 TRM 13.3.4 and and Basis, Basis, Ver.

Ver. 3.0 3.0 TS 3.9.2 and Basis, Amendment 146 146 (U-l),

(U-I), Amendment 137 137 (U-2)

UOP-4. 1, CONTROLLING PROCEDURE FOR REFUELING, Ver. 51.0 UOP-4.1, TO DISCUSS

'1"0 [)ISCUSS with the examiner:

Due to procedure rules Due rules of usage, a candidate may stop performing performing the steps 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.

FNP HLT-33 FNP HLT-33ADM ADMIN IN A.1.1.SRO A.1.1.SRO HANDOUT HANDOUT #2 #2 Pg Pg 11 of of 11 CONDITIONS CONDITIONS Based on Based on the conditions you the conditions you identified identified evaluate evaluate TS TS and and TRM requirements and TRM requirements and perform perform the the following:

following:

a.a. List all List all TS CONDITIONS, REQUIRED TS CONDITIONS, REQUIRED ACTIONS ACTIONS and and COMPLETION COMPLETION TIMESTIMES forfor LCOs LCOs notnot met, ifany.

met, if any.

FNPHLT-33ADMIN FNP HLT-33 ADMIN A.1.1.A HANDOUT Page 11 of 11 Page CONDITIONS FNP-l-UOP-4.1, Appendix 6, When I tell you to begin, you are to perform or evaluate all steps FNP-I-UOP-4.1, 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 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> ago.

b. RCStempis RCS 100°F.

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 chemistrys request.

h. FNP-1-STP-18.4, Containment Midloop and/or Refueling Integrity Verification and FNP-I-STP-18.4, Containment Closure, was completed yesterday at 1400.

i.

I. CTMT Main Purge system is in operation.

j.

J. The equipment hatch and all containment air locks are currently closed.

k. Applicable equipment can be assessed using the provided photographs.

1.I. of FNP-1-UOP-4.1, Appendix 6.

You have been directed to perform or evaluate all steps ofFNP-I-UOP-4.1,

m. Determine whether or not all Core Alterations initial conditions are satisfied.

07/02/09 06:39:16 07/02/0906:39: 16 FNP-I-UOP-4.1 FNP-1-UOP-4.1 APPENDIX 6 VERIFICATION VERIFICA CONDITION S TION OF INITIAL CONDITIONS PRIOR TO CORE ALTERATIONS Performed by: ________________________

Perfurmedby: Date Reviewed by:

by: Date This This appendix appendix consists consists of of 22 pages pages Version 51.0 Version 51.0

07/02/0906 07/02109 06:39: 16 39 16 FNP-1-UOP-4.1 FNP-1-UOP-4 I APPENDIX APPENDIX 66 APPENDIX 66 APPENDIX VERIFICATION VERIFICA nON OF OF INITIAL INITIAL CONDITIONS CONDITIONS PRIOR TO PRIOR TO CORE CORE ALTERA ALTERATIONS nONS 1.0

Purpose:

Provide separate guidance for specific initial initial conditions which will be needed to once due to core alterations be verified more than once alterations occurring at various time during an outage during outage period.

2.0 Initial Conditions:

2.1 The version of this appendix is the current version. (OR 1-98-498) 1-98-498) 2.2 This appendix is correct for the unit for which the task applies. (OR 1-98-498) 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3.1 The direct communications system between the control room and the reactor

_1- / cavity is verified available for use within one hour prior to core alterations.

CAUTION: Gamma-Metrics source range channel may only be used as a The Gamma~Metrics back~up back-up to N~31 N-31 or N~32 N-32 during certain core configurations. The Refueling Coordinator should be consulted ifN-31 N~32 becomes if N-31 or N-32 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 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to any core alterations. Trip functions and associated TSLBs are not required required for Mode 66 or core alterations.

3.2.1 3.2.1 Source Source Range Nuclear Nuclear Instrument, Channel N-31 3.2.2 3.2.2 Source Range Range Nuclear Instrument, Channel N-32 3.2.3 3.2.3 Gamma-Metrics Gamma-Metrics Neutron Flux Flux Monitor, Monitor, Channel Channel N-48 of2 Page 11 of Page 2 Version 51.0 Version 51 .0

07/02/09 06 39 16 07/02/0906:39:16 FNP-I-UOP-4.1 FNP-1-UOP-4 1 APPENDIX 66 APPENDIX 3.3 3.3 The reactor The reactor coolant coolant system system boron boron concentration is> 2000 concentration is:::: 2000 ppm.

ppm.

3.4 3.4 The following The following radiation radiation monitors monitors are in operation are in operation per per FNP-l-S0P-45.0, FNP-1-SOP-45.0, RADIATION RADIA MONITORING SYSTEM, nON MONITORING SYSTEM, or or required required action action isis being being taken taken per per Tech. Specs Tech. Specs 3.3.6, 3.3.7, and 3.3.6, 3.3.7, and 3.3.8, 3.3.8, and and TRTR 13.3.4.

13.3.4.

3.4.1 3.4.1 R-5 fuel storage Spent fuel R-5 Spent storage or or portable monitoring instrumentation instrumentation usedused to monitor SFP area at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (for fuel (for fuel movement in SFP).

3.4.2. R-25A or 3.4.2. or B B Spent fuel storage storage - Gaseous (for fuel fuel movement in SFP).

3.4.3 R-24A or B B - Containment purge system

- system with main main or mini purge in operation.

3.4.4 R-35A or B - Control Room HVAC 3.5 FNP-1-STP-1 8.4, CONTAINMENT Refueling integrity has been verified per FNP-l-STP-18.4,

_/-/ MIDLOOP AND/OR REFUELING INTEGRITY VERIFICA VERIFICATION nON AND CONTAINMENT CLOSURE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of core alterations.

alterati ons.

3.6 jf 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)

MM is available to shut the containment equipment hatch, a door in the personnel air lock, and a door in the auxiliary air lock within two hours after notification and direction from the control room.

/ 3.6.2 For the equipment hatch, the surveillance is current for SR 3.9.3.3, i.e.,

FNP-0-STP-610.0 FNP-0-STP-61 0.0 has been completed by Maintenance within the last seven days Page Page 22 of of2 2 Version 51.0 Version 51.0

oCD o NUCLEAR INSTRUMENTATION PROTECTION CHANNEL II SOURCE RANGE V d

-.I (104

/

7J N1C55N10031 CHANNtL Off TEST TRIP I I Pung Coro1 Pc LOSS OF O!TgCTOfl VOLT. Fuses wrtout prior Deacivaon w4 Scn Ct EvacuaDon Maim 118V, 11 V 5A, "J' }'\(

III .; III sm POll/ER POI/,TI\ I 11~V. 3A.AC 118V ~;A, AC CO'lmOL COf4UOL POWER POWER I

oC o o0 INSTRUMENTATION NUCLEAR INSTRUMENTAT ION PROTECTION CHANNEL II PROTECTION II SOURCE RANGE L -

Ni C55NIO32 INSTRUMCWr CHANNEL ON POWER ON TEST CONTROL LGSS or POWER ON OCIECTOR VOLT. Ft.se pror Dea-iaor w!

LEVEL TRIP OPERATION SELECTOR HIGH FLUX SOUndCT AT SHUTDOWN Evacuaon Jarm AOJ fJC:rA I F r:rr-!L 6LOC$

\ ,

F I

IISV, 11 ~l V 5A,AC 5fl." l'.. C PfALi S / 118V 5A,AC 118V, 51\ Ae INSTR III ~ r I ~ CCHIll

2 SGs Avail with loops filled (Ref.

2. LINE 1:22 2) Zero (0) written on the line for S / U step 2.7).- evaluate SG availability: 1.

item 1.
• SG tubes filled and vented; considered filled oo Midloop f:. filled and vented remained 1 00 psig and vented if RCS has remained::::l and <
< 100 psig since last fill and vent.
• • 3. LINE 2:Cavity level::::
level> 152' 152 9" 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.
• • level> 126'

5. LINE 4:RCS level:::: 126 6" 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 Coolin "What Cooling in?" in?
• • 8. Evaluates Core Cooling condition 8) Circle around ORANGE S S / UU 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.
Terminate STOP TIME CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number. FNP HLT-33 ADMIN FNP HLT-33 ADMIN A.1 .2.S A.1.2.S Page 44 of Page of 55 GENERAL

REFERENCES:

GENERAL

REFERENCES:

1. FNP-0-UOP-4.0,

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

2. KA: G2.1.25

2. KA: G2.l.25 RO RO 3.9 3.9 SRO SRO 4.2 4.2 GENERAL TOOLS AND EQUIPMENT:

I. References

1. References to to be accessed via classroom be accessed classroom computer computer (using (using exam exam 10 ID logon) logon) and and Exam Exam Reference Reference disk/files only.

of FNP-0-UOP-4.0 Table A, Table B, Appendix 11

2. Provide copy ofFNP-0-UOP-4.0

3. Pen/Pencil

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

Critical ELEMENT justification:

STEP Evaluation I.

1. Critical - this is first of the two major objectives of the task. Utilization of the plant parameters and selection of the appropriate table are required to properly assess Shutdown Core Cooling function.

2.

Critical - Each line item is critical to evaluate proper assessment of each parameter.

3.

The aggregate effect of errors made within each line could result in obtaining the 4.

correct end point; therefore each sub-step must be evaluated to ensure examinee is 5.

correctly assessing the parameters.

6 6.

7. This is NOT a critical element since documentation of this summation is not procedurally driven nor will failure to complete this element necessarily impact the outcome.

8. Critical - This is the final objective of the task; proper assessment of this function is required to identify the need of mitigating actions necessary to ensure the health and safety of the public is not jeopardized.

COMMENTS:

References expected to be utilized:

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

Header information is not required for this Task; but if requested use current date and time.

Prepared By:-=====~__ ULv * .J....._--'-Time:_IH_H_M_MI App-l, Fig 2 Evaluated 0 SHUTDOWN SAFETY SHUTDOWN SAFETY FUNCTIONI FUNCTION! CRITERIA CRITERIA CONDITION CONDITION (No/False=0, Yes/True=l, (NolFalse=O, Yes/True=l, Use Use number number within within range range when when required) required) (Circle (Circle Condition)

Condition)

REACTIVITY REACTIVITY Subtotal Subtotal Condition Condition AOP AOP J.I. No Core No Alterations in Core Alterations Progress in Progress 0-1 0-I RED RED 41 41 2.

2. Number of Number of Boration Boration Flow Flow Paths Paths (0, 1, 2) (Ref (0, 1,2) (Ref step 2.13) step 2.13) 22 ORANGE ORANGE 41 41 3.

3. RCS Boron:

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

4. Source Range Source Instrumentation Available Range Instrumentation Available 55 GREEN GREEN 4.

(GREEN ifDefueled)

(GREEN if Defueled)

Reactivity Subtotal Reactivity Subtotal CORE CORE COOLINGCOOLING Subtotal Subtotal Condition Condition AOP AOP I.1. SGs A

2: 2 SGs Avail vail with loopsloops filled filled (Ref step 2.7) 0 0-IL_

• _
• _~IiP.
• Q,- RED _
• _
• _
• _4f 42 _
• _ * "':'

2.

2. Cavity level 2152'9" 1529 0 2-3 ORANGE 42

• _22 _ F- '4" ....... )-"ttI':<M" .... 4'2" ......

3.

3. RHR Subsystems Available (0, RHR Subsystems (0, lor 1 or 2) 2)

_00 _ 25 GREEN GREEN 4.

4. RCS level:2:

RCS level 126' 126 6" 6 (GREEN ifDefueled)

(GREEN if Defueled) Min Mm required is to

5. Time to saturation>

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

J. II "A" A Train DG Available 0-2 RED including the

2. B Train DG Available I1 "B" 3 ORANGE subtotal or the AOP

3. F 4160 V BUS normal (Aligned to A SUT) SOT) 4-5 YELLOW 6 GREEN is not required.

4. G 4160 V BUS normal (Aligned to B SUT)

5. 2 Feeds available to the HV Switchyard (0, I1 or 2)

Power Availability Subtotal Power Availabilitv Subtotal CONTAINMENT Subtotal Condition AOP I.

I. Refueling Integrity Set 0-1 0l 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 77 GREEN Short Notice (GREEN ifDefueled) if Defueled)

5. level 126' RCS level:2: 126 6"6 (3 pts)

Containment Subtotal INVENTORY Subtotal Condition AOP 1.

J. Refueling Cavity :2: 23 Feet Feet (142 ) Above Fuel (142' 11") 00 RED 45

2. LHSI Pump/Flowpath PumpfFlowpath Available I1 ORANGE 45

3. I-IHSI HHSI PumpfFlowpath PumpfFlowpath Available 22 YELLOW 45

4. RCS is Intact below the Reactor Vessel Flange 3-4 GREEN (GREEN if ifDefueled)

Defueled)

Inventory Subtotal RCS INTEGRITY RCS INTEGRITY Subtotal Condition Condition AOP AOP I.

I. SfG Manways or Nozzle Dams All S/G Dams Installed 0-I 0-1 ORANGE ORANGE 46 2.

2. RCS is Intact below the Reactor Vessel Flange 22 YELLOW 46 3.

3. Pressurizer level < < 100%

100% 33 GREEN RCS Integrity (GREEN if if Defueled)

Intee:ritv Subtotal SPENT SPENT FUEL FUEL COOLING COOLING Subtotal Subtotal Condition Condition AOP AOP I.

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

2. AA TmTrn SFP Cooling available SFP Cooling available 55 ORANGE ORANGE 47 47 3.

3. BB TmTrn SFP SFP Cooling Cooling available 66 YELLOW YELLOW 47 47 77 GREEN GREEN 4.

4. :2: 22 SFP SFP Makeup Makeup Sources Sources (RWST, (RWST, DW, DW, RMW RMW to to Blender, Blender, Boric Boric Acid Acid to to Blender.

Blender, RHT RHT to to transfer transfer canal canal with weir gate removed) weir gate removed)

SFP Subtotal SFP Subtotal Time Time to to saturation saturation If IE core core cooling cooling werewere lost:

lost: 00 hours flours 9.2 9.2 minutes minutes Current Version Current Version Page 66 of Page of 18 18

FNPHLT-33ADMIN FNP HLT-33 ADMIN A.1.2S A.1.2S HANDOUT HANDOUT Pg Pg 11 of of 1I CONDITIONS CONDITIONS When II tell When tell you you to begin, you to begin, you are are toto determine determine the the time time to to saturation saturation andand prepare prepare the the CORE CORE COOLING SECTION ONLY COOLING SECTION ONLY of a shutdown of a shutdown safety safety assessment assessment on Unit 11 per on Unit per FNP-O-UOP-4.0, FNP-O-UOP-4.O, Appendix 1, Appendix 1, step step 4.3 4.3 and and step step 4.4.

4.4. The The conditions conditions under under which which this this task task is is to to be be performed performed are:

are:

a. Unit

a. Unit 1us in aa Refueling is in Refueling Outage, Outage, and and has has been shutdown shutdown for for 120 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />.

hours.

b. 1A 1A SGSG wide range level wide range level is is 74%;

74%; IB113 SG SG wide range level level is is 75%;

75%; 1ICC SG SG wide range level level is is 10%.

10%.

c. RCS temperature is is 120°F.

120°F.

d. The RCS is at mid-loop with aa FULL FULL core.

core.

e.

e. Both trains of RHR are in operation in the cooldown mode.

f.f. Mid-loop integrity per STP-18.4STP-1 8.4 has been verified current.

g. The IPC is not available.

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

i. You are directed to determine the time to saturation and prepare the CORE COOLING 1.

SECTION ONLY of a shutdown safety assessment on Unit 11 per FNP-0-UOP-4.0, Appendix 1, step 4.3 and step 4.4.

11/13/09 12:03:44 11113/09 12:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 TABLE TABLE AA TABLE A TABLE A Power-Uprated Power-Up rated Unit Unit Time ToTo Saturation: FullFull Core Core Initial Temperature Assumed Initial Temperature == lOO°F 100°F Time Time To Time To Time To Time To After Saturation Saturation Saturation Saturation Saturation Saturation Saturation Saturation RCS Shutdown Shutdown at Midloop 3 ft Below Flange Full Reactor Cavity Full (hours) (mm)

(min) (min)

(mm) (hours) (hours) 40 7.7 10.5 5.6 1.3 60 8.7 11.9 6.3 1.4 80 9.5 13.0 l3.0 6.9 1.6 100 100 10.4 14.2 7.5 1.7 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 l3.9 19.0 10.1 2.3 336 336 17.1 17.l 23.4 12.4 12.4 2.9 504 20.8 28.5 15.1 15.1 3.5 VOLUME VOLUME REFERENCE TABLE Midloop Volume (ft3): 945 Volume: 33 ft Below Below Flange Flange (ft3) 348 348 Total ==

Total 1293 1293 Volume:

Volume: Full Full Reactor Reactor Cavity Cavity (ft3)

(ft3) 39750 39750 Total ==

Total 41043 41043 Volume: RCS Full Volume: RCS Full (including (including Pzr) pzr) (ft3)

(ft3) 9591 9591 Page 11 of Page of33 Version 36.0 Version 36.0

11/13/09 12:03:44 11/13/09 12:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 TABLE TABLE AA TABLE A TABLE A Power-Up Power-Upratedrated Unit Unit Time To Saturation: Full Full Core Initial Temperature Assumed Initial Temperature == 120°F 120°F Time Time To Time To Time To Time To After Saturation Saturation Saturation Saturation Saturation RCS Shutdown at Midloop 3 ft Below Flange Full Reactor Cavity Full (hours) (mm)

(min) (min)

(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 1.4 120 120 9.2 12.6 12.6 6.7 1.6 140 140 9.8 13.4 13.4 7.1 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 19.1 10.1 10.1 2.4 504 17.0 17.0 23.3 12.3 12.3 2.9 VOLUME REFERENCE TABLE Midloop Volume (ft3): 945 945 Volume: 33 ft Below Below Flange Flange (ft3) 348 348 Total ==

Total 1293 1293 Volume: Full Volume: Full Reactor Reactor Cavity Cavity (ft3)

(ft3) 39750 39750 Total =

Total 41043 41043 Volume:

Volume: Full RCS (including Full RCS (including Pzr) pzr) (ft3)

(ft3) 9591 9591 Page 22 of Page of33 Version 36.0 Version 36.0

I 1/13/09 12:03:44 11113/0912:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 TABLE TABLE AA TABLE A TABLE A Power-Uprated Power-Up rated Unit Unit Time To Time To Saturation:

Saturation: FullFull Core Core Assumed Initial Temperature = 140°F Initial Temperature 140°F Time Time To Time Time To Time To After Saturation Saturation Saturation Saturation Shutdown Time To Saturation Saturation Shutdown at Midloop Below Flange 3 ft Below Full Reactor RCS RCS Full Full (hours) (mm)

(min) (min)

(mm) Cavity (hours)

(hours) 0.8 40 4.9 6.7 3.5 60 5.6 7.6 4.0 0.9 4.4 1.0 80 6.1 8.3 9.1 4.8 1.1 100 6.6 5.2 1.2 120 7.2 9.8 1.3 140 7.6 10.4 5.5 5.9 1.4 160 8.1 11.1 6.1 1.4 180 8.5 11.6 200 8.9 1.5 12.1 6.4 336 1.8 10.9 14.9 7.9 504 18.2 2.2 13.3 9.6 VOLUME REFERENCE TABLE Midloop Volume (ft3): 945 Volume: 33 ft Below Below Flange Flange (ft3) 348 348 Total == 1293 1293 Volume: Full Reactor Cavity (ft3)

(ft3) 39750 39750 Total ==

Total 41043 41043 Volume: Full Full RCS (including Pzr) pzr) (ft3) 9591 9591 Page Page 33 of of33 Version 36.0 Version 36.0

11/13/09 12:03:44 11113/0912:03:44 FNP-0-UOP-4.0 TABLE B TABLEB TABLE B TABLEB Power-Uprated Power-U prated Unit Time To Saturation: One-Third New Fuel 100°F Assumed Initial Temperature == lOO°F Time Time To Time To Time To Time To After Saturation Saturation Saturation Saturation RCS Shutdown at Midloop 3 ft Below Flange Full Reactor Full (hours) (mm)

(min) (mm)

(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: 33 ft Below Flange (ft3) 348 Total == 1293 Volume: Full Reactor Cavity (ft3) 39750 Total == 41043 Volume: Full RCS (including Pzr) pzr) (ft3) 9591 Page 11 of of33 Version 36.0

11/13/09 12:03:44 11113/09 12:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 TABLE TABLE BB TABLE B TABLEB Power-Uprated Power-Up rated Unit Unit Saturation: One-Third New Fuel Time To Saturation:

Initial Temperature Assumed Initial Temperature == 120°F 120°F Time Time To Time To Time To Time To After Saturation Saturation Saturation Saturation Saturation Saturation RCS Shutdown at Midloop 3 ft Below Flange Full Reactor Full (hours) (mm)

(min) (mm)

(min) Cavity (hours)

(hours) 100 12.8 17.5 9.2 2.2 200 17.1 23.4 12.4 2.9 300 20.2 27.6 14.6 3.4 400 22.5 30.8 16.3 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):

MidloopVolume 945 Volume: 33 ft Below Flange (ft3) 348 Total == 1293 1293 Volume: Full Full Reactor Cavity (ft3) 39750 39750 Total = 41043 41043 Volume: Full RCS (including Pzr) pzr) (ft3) 9591 9591 Page of3 Page 22 of 3 Version 36.0 Version 36.0

11/13/09 12:03 11113/09 12:03:44

44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 TABLE TABLE BB TABLEB TABLE B Power-Uprated Unit Power-Uprated Unit Time To Time To Saturation:

Saturation: One-Third One-Third NewNew Fuel Fuel Assumed Initial Assumed Initial Temperature Temperature == 140°F 140°F Time Time To Time To Time To Time To After Saturation Saturation Saturation Saturation Saturation Saturation Saturation RCS Shutdown Shutdown at Midloop 3 ft Below Flange Full Reactor Full Full (hours) (mm)

(min) (mm)

(min) Cavity (hours)

(hours) 100 100 10.0 10.0 13.6 13.6 7.2 1.7 1.7 200 13.3 18.2 9.6 2.2 300 15.7 21.5 11.4 2.7 400 17.5 24.0 12.7 3.0 500 19.8 27.1 14.3 3.3 600 22.0 30.1 15.9 3.7 700 23.7 32.5 17.2 4.0 800 25.7 35.2 18.6 4.3 VOLUME REFERENCE TABLE Midloop Volume (ft3): 945 Volume: 33 ft Below Flange (ft3) 348 Total =

= 1293 Volume: Full Full Reactor Cavity (ft3) 39750 Total Total == 41043 Volume: Full RCS (including Pzr) pzr) (ft3) 9591 Page Page 33 of of33 Version 36.0 Version 36.0

11/13/09 12:03:44 11113/09 12:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 1I FARLEY NUCLEAR FARLEY NUCLEAR PLANT PLANT SHARED SHARED OPERATING PROCEDURE UOP-4.0 UNIT OPERATING APPENDIX 11 APPENDIX 1.0 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 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 plants ability to perform the associated safety function is Yellow Condition - The plant's reduced but is at an acceptable level.

2.3 plants ability to perform the associated safety function Orange Condition - The plant's has been severely reduced and steps should be taken to minimize the amount of time in this condition.

2.4 plants ability to perform the associated safety function is in Red Condition - The plant's 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 2.7 One or More SGs Available - A S/G is available to remove heat if the tubes are

- are filled and vented, the wide range level is> is ~ 75%, a steam steam flow path to the atmosphere can be made available with minor valve manipulations and a means of of adding water to the S/G via the auxiliary feed water system exists.exists. The S/G tubes are are considered and vented if considered filled and if the RCS has been been maintained maintained greater greater than or or equal equal to 100 psig to 100 psig since since the the last last RCS RCS fill andand vent.

vent.

2.8 2.8 RHR Subsystems Subsystems Available - The RHR

- RHR system is capable of removing heat heat from the the RCS.

RCS.

Page Page 1I of of 18 18 Version 36.0 Version 36.0

11/13/09 12:03:44 11113/09 12:03 :44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX II 2.9 2.9 One DIG One Available - The D/G Available - The selected selected DIG DIG is is capable capable of of being being started started (either (either manually or manually or automatically) automatically) and and supplying supplying 41604160 VV power power to to its its respective respective bus.

bus.

2.10 2.10 Equipment Hatch Equipment Hatch & Airlocks Capable

& Airlocks Capable of of Being Being Closed Closed onon Short Short Notice Notice - The The equipment hatch equipment hatch meets meets this definition definition when when the MCRT is the MCRT is established.

established. TheThe personnel and personnel and aux airlocks meet aux airlocks meet this definition when this definition when aa routine routine check check ofof the the hoses hoses and cables going and going through the airlocks airlocks reveals that at least one door door in each airlock can be closed in less than the current time to boil. (AI (Al 2008207932) 2.11 HHSI Pump I/ Flow Path Available - A charging

- charging pump is capable capable of of injecting injecting from the RWST which contains> 50,000 water into the RCS from 50,000 gallons of water.water.

Only minor valve manipulations manipulations are required.

2.12 LHSI Pump I Flow Path Available - A RHR pump is capable of injecting water Pump/Flow -

into the RCS from the RWST which contains> 50,000 gallons of water. Only manipulations are required.

minor valve manipulations 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 FNP-1-STP-2.1 FNP-2-STP-OR FNP-2-STP-2.l 2.l ,BORON

, BORON INJECTION FLOW PATH VERIFICATION VERIFICATION AND BORIC ACID TRANSFER PUMP OPERABILITY OPERABILITY TEST, MODES 5 & &6 FNP-1-STP-3.2 OR FNP-2-STP-3.2, AND by a current FNP-I-STP-3.2 FNP-2-STP-3.2, BORATED WATER OPERABILITY TEST MODE 5, SOURCE OPERABILITY 6.

5,6.

Additionally, Normal charging can be considered an available boration flow path Additionally, under the following conditions:

2.13.1 QIE2IMOV8IO7 and QIE21MOV8108 QIE21MOV8107 Q1E2IMOV8IO8 are open, OR Q2E21MOV8IO7 and Q2E21MOV8108 Q2E21MOV8107 Q2E21MOV8IO8 are open.

2.13.2 With one of the following charging pump requirements met.

• IA or 2A Charging Pump available
• B Charging Pump Available with Ql IIB E2 1 MOV8 I 32A and B QIE21MOV8132A B open, OR 2B Charging Pump Available with Q2E2 Q2E2IMOV8132A I MOV8 I 32A and B B open
• 1C IC Charging pump available with QIE2IMOV8 QIE21MOV8132A I32A and B B open, OR 2C Charging pump available with Q2E2IMOV8 Q2E21 MOV8132A I32A and B B open Page 22 of Page of 118 8 Version 36.0 Version 36.0

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44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 1I 3.0 3.0 Precautions and Precautions and Limitations Limitations 3.1 3.1 The Shift The Shift Supervisor Supervisor will will evaluate evaluate the the affect affect of of removing removing shutdown shutdown safety safety equipment from equipment service. If from service. If proposed proposed changes changes toto the the schedule schedule appear appear toto reflect reflect aa reduction in reduction in the the key key safety safety functions, functions, refer refer the the proposed proposed changes changes to the Outage to the Outage Manager for Manager for assessment assessment per FNP-0-AP-94, FNP-0-AP-94, OUTAGE OUTAGE NUCLEAR SAFETY, SAFETY, prior to implementing the changes.

3.2 appropriate AOP-40 series The appropriate series procedure will be implemented implemented upon unexpected into or 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 FNPs current position is that the plant will not be intentionally placed in this condition.

FNPs commitment to NUMARC 91-06.

Review FNP's 9 1-06.

3.4 Intentional entry into an orange condition must be approved by the Outage Manager or his designee prior to entry into that condition and documented per FNP-0-AP-94.

3.5 Intentional entry into a yellow condition must be approved by the Shift Manager or Operations Superintendent prior to entry into that condition.

3.6 Notify the Outage Manager immediately if a red condition or an unexpected orange condition exists.

4.0 Instructions NOTE: ** The Shutdown Safety Assessment form may be a two-side copy. copy .

• The Shift Supervisor will ensure that the appropriate Shutdown Safety Assessment Form is completed at about 0200 and 1400 when in Mode 4, Mode 5, Mode 6 or defueled. (CR 2004102447) 4.1 Obtain a copy of the appropriate Shutdown Safety Assessment form. For modes 5, 6, and defueled use Figure 1A IA and for mode 4 use Figure 1lB. B.

4.2 Fill in in the header information on on the form.

• • Unit Unit
• Prepared By By
• • Date Date
• • Time Time Page of 18 Page 33 of 18 Version 36.0 Version 36.0

11/13/09 12:03:44 11113/09 12:03 :44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX 1I APPENDIX 4.3 4.3 IF in IF in mode mode 55 or or 6, THEN determine 6, THEN determine thethe time time toto saturation saturation for existing plant for existing plant conditions using the conditions using the IPC IPC (preferred)

(preferred) or or FNP-0-UOP-4.0 FNP-0-UOP-4.0 Table Table AA or or B.B. Enter Enter time time on Figure on Figure 11A A ofofAppendix Appendix 1.I.

4.4 4.4 Evaluate the Evaluate the criteria criteria listed listed below below each each Shutdown Shutdown Safety Function as Safety Function as follows.

follows.

NOTE:

NOTE: Refer to Refer Definitions to to Definitions to assist assist inin the the evaluation evaluation as as appropriate.

appropriate.

I 4.4.1 4.4.1 IF the IF the reactor reactor isis defueled, defueled, THEN N/ N/A blanks for the blanks A the for all all Safety Safety Functions except Functions except power power availability availability and and spent spent fuel fuel cooling.

cooling.

4.4.2 criteria is met, THEN place aa 1I in its IF the criteria its blank oror use the the number/range of number/range of numbers listed in 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 corresponding to the subtotal.

and circle the condition corresponding 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 requirements..

4.6.2 Check the box on Figure IA 1A or lB1B to indicate the review of the Figure 22 posting requirements {A1 {AI 2001203573 2001203573}. ).

4.7 4.7 If a red, orange, or yellow condition currently exists for any Safety Safety Function due to an intentional intentional entry, verify 4.7.1 4.7.1 Appropriate Appropriate approval per per FNP-0-AP-9 FNP-0-AP-94 has been 4 has been obtained, obtained, andand 4.7.2 4.7.2 Contingency Contingency Actions Actions per per Table Table I1 have been performed have been performed for for the the affected affected Shutdown Shutdown Safety Safety Functions.

Functions.

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11/13/09 12:03:44 11113/09 12:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 1I 4.8 4.8 Evaluate the Evaluate the activities activities planned planned for for the the next next 12 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> hours to to determine determine if if the the plant plant may may enter aa red, orange, or potentially enter or yellow condition.

4.8.1 4.8.1 jf intentional entry into IF into aa red red condition is expected THEN entry must be approved by the Nuclear Plant Plant General Manager andand documented documented per FNP-0-AP-94, FNP-0-AP-94, OUTAGE NUCLEAR SAFETY. FNP's FNPs current current position is is that the plant will not be intentionally placed in this condition. Review FNPs commitment to NUMARC 91-06.

FNP's 4.8.2 fl intentional entry into an orange condition is expected THEN IF 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 j!

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 991-06, 1-06, Guidelines Guidelines For For Industry Actions To Assess Shutdown Shutdown Management.

4.2 4.2 IOCFR5O.65 10CFR50.65 (a)(4)

(a)(4) 4.3 4.3 NUMARC NUMARC 93-01,93-01, Section Section 11, 11, Assessment Assessment of of Risk Risk Resulting Resulting from Performance Performance ofof Maintenance Maintenance Activities, Activities, February February 2, 2, 2000.

2000.

4.4 4.4 FNP-0-AP-94, FNP-0-AP-94, OUTAGE OUTAGE NUCLEAR NUCLEAR SAFETY.SAFETY.

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11/13/09 12:03:44 11113109 12:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 1I Figure lA Figure IA SHUTDOWN SAFETY SHUTDOWN SAFETY ASSESSMENT ASSESSMENT (Modes (Modes 5,5, 66 and and Defueled)

Defueled)

Unit:

Unit:_ Prepared 8y:

Prepared _ _ _ _ _ _ _ _ Date:

By:_________________ Date:_ _ _ _Time:___

Time:______ App-l, App-I, Fig Fig 22 Evaluated Evaluated 0El SHUTDOWN SAFETY SHUTDOWN SAFETY FUNCTION/

FUNCTION! CRITERIA CRITERIA CONDITION CONDITION (No/False=O, (No/False Yes/TrueI, 0, Yes/True Use number 1, Use number within range when required) ~,

(Circle (Circle Condition)

Condition)

REACTIVITY REACTIVITY Subtotal Subtotal Condition Condition AOP AOP I.

1. No Core Alterations in Core Alterations in Progress Progress 0-1 0-1 RED RED 41 41 2.

2. Number of Boration Flow Paths (0, of Boration (0, I,1, 2)

2) (Ref (Ref step 2.13) step 2.13) 22 ORANGE ORANGE 41 41 3.

3. RCS Boron: CSDfRefueling Concentration Boron: CSO/Refueling Concentration 3-4 34 YELLOW 41 41 4.

4. Source Range Source Instrumentation Available Range Instrumentation Available 55 GREEN GREEN (GREEN (GREEN if if Defueled)

Defueled)

Subtotal Reactivity Subtotal Reactivity CORE COOLING CORE COOLING Subtotal Subtotal Condition Condition AOP AOP 1.

1. z 22 SGs AAvailvail with loops filled (Ref step 2.7) 0-1 RED 42

2. Cavity levelz 1529 level 152'9" 2-32-3 ORANGE 42 4 YELLOW 42

3. RHR Subsystems Available (0, I1 or 2) 2':5 GREEN GREEN

4. level 126' RCS levelz 126 6" 6

(GREEN (GREEN if if Defueled)

Defueled) 5.

5. saturation > 30 Time to saturation> 30 minutes OR RCS press> 325 325 psig with at at least least one RCP available for operation and at least one SG available Core Cooling Subtotal POWER AVAILABILITY Subtotal Condition AOP I.

1. I "A"A Train OG DG Available 0-2 RED 43

2. I1 "B" B Train DG Available 33 ORANGE 43

3. F 4160 V BUS normal (Aligned to A SUT) 4-5 45 YELLOW 43 6 GREEN

4. G 4160 V BUS normal (Aligned to B SUT)

5. 2 Feeds available to the HV Switchyard (0, (0. I1 or 2)

Power Availability Subtotal CONTAINMENT CO NT AINMENT 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 Equipment Hatch & & Air Locks Closed or Capable of Being Closed on 77 GREEN 4.

Short Notice (GREEN if Defueled) Defucled)

5. RCSlevel RCS 126 6" levelz 126' 6 (3 pts)

Containment Subtotal INVENTORY Subtotal Condition AOP I.

1. Refueling Cavity z 23 Feet (142l) (142'1") Above Fuel Fuel 00 RED 45

2. LHSI Pump/Flowpath PumplFlowpath Available I1 ORANGE ORANGE 45 45 3.

3. HHSI Pump/Flowpath Pump/Flowpath Available 22 YELLOW 45

4. RCS is Intact below the Reactor Vessel Flange 3-4 3-4 GREEN (GREEN if ifDefueled)

Defueled)

Inventory Subtotal RCS INTEGRITY INTEGRITY Subtotal Subtotal Condition AOP AOP I.

1. All S/G Manways or All S/G or Nozzle Dams Installed Nozzle Dams Installed 0-1 0-I ORANGE ORANGE 46 46

2. RCS isis Intact below the Reactor Vessel Vessel Flange Flange 22 YELLOW YELLOW 46 46 3.

3. Pressurizer level Pressurizer level << 100%

100% 33 GREEN GREEN (GREEN if (GREEN ifDefue1ed)

Defueled)

RCS Integrity Subtotal RCS Integrity SPENT SPENT FUEL FUEL COOLING COOLING Subtotal Subtotal Condition Condition AOP AOP 1.

1. level z 23 SFP level SFP 23 feet (1516)

(151 '6") above above fuel fuel (4 (4 pts) pts) 0-4 0-4 RED RED 47 47 2.

2. A Tm Tm SFP SFP Cooling Cooling available available 55 ORANGE ORANGE 47 47

3. BB Tm SFP Cooling Tm SFP Cooling available available 66 YELLOW YELLOW 47 47 3.

77 GREEN GREEN 4.

4. z 22 SFP SFP Makeup Makeup Sources Sources (RWST, (RWST, DW, OW, RMW RMW to to Blender, Blender, Boric Boric Acid Acid to to Blender, Blender, RHT RHT to to transfer transfer canal canal with with weir weir gate gate removed) removed)

SFP SFP Subtotal Subtotal Time Time to saturation Jf to saturation IF core core cooling cooling were were lost:lost: nours hours minutes minutes Page Page 66 ofof 18 18 Version 36.0 Version 36.0

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Unit:_ _ Prepared Unit Prepared By: By:________________

_ _ _ _ _ _ _ Date: Date:_ _ _ _Time:___Time:______ App-l, App-I, Fig Fig 22 Evaluated Evaluated 0 SHUTDOWN SAFETY SHUTDOWN SAFETY FUNCTION/

FUNCTION! CRITERIA CRITERIA CONDITION CONDITION (Circle Condition)

(Circle Condition)

(No/FalseO, Yes/True=

(No/False=O, YeslTrue=1, 1, Use number within range range when when required) required)

REACTIVITY REACTIVITY Subtotal Subtotal Condition Condition AOP I. No

1. No positive positive reactivity reactivity changes changes in Progress in Progress --- 0-1 0-1 RED RED 41 41

2. Number

2. Number of Boration Flow of Boration Flow Paths Paths (0, (0, 1, 2) (Ref

1. 2) (Ref step step 2.13) 2.13) --- 22 ORANGE ORANGE 41 41

3. RCS

3. RCS Boron:

Boron: CSO CSD boron boron concentration concentration 3-4 3-4 YELLOW YELLOW 41 41

4. Number of Source Range Instrumentation Available 5 GREEN Reactivity Subtotal Reactivity ---

CORE COOLING Subtotal Condition AOP AOP I.

1. 22 SGs SGs Available (2 (2 pts if2 if 2 S/G's S/Gs Available (Ref (Ref step step 2.7) --- 0-1 RED 42

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

3. PRZ level within normal operating band 4 YELLOW 42

4. Margin > 16° F RCS Subcooling Margin> --- 25 GREEN Core Cooling Subtotal ---

POWER A AVAILABILITY VAILABILITY Subtotal Condition AOP

1. 11 "A" A Train OGDG Available 0-2 RED 43

2. 11 "B" B Train OGDG Available

--- 33 ORANGE 43

3. F 4160 V BUS normal (Aligned to A SUT) ---

4-5 YELLOW 43

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

5. 2 Feeds available to the HV Switchyard (0, (0. 11 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

--- 00 RED 45

2. LHSI Pump/Flowpath Available 1I ORANGE 45

3. HHSI Pump/Flowpath Available 22 YELLOW 45

4. Normal make-up capability available 3-4 3-4 GREEN Inventoiy Inventory Subtotal ---

RCS INTEGRITY Subtotal Condition AOP I.

1. LTOP LTOP TECH TECH SPEC SPEC METMET ---

0-1 0-1 ORANGE ORANGE 46

2. RCS/PRZ RCS/PRZ cooldown cooldown rate << tech spec allowable 22 YELLOW YELLOW 46 46 3.

3. Pressurizer operable operable perper tech specs specs --- 33 GREEN RCS RCS Integrity Integrity Subtotal Subtotal SPENT SPENT FUEL FUEL COOLING COOLING Subtotal Subtotal Condition Condition I.

1. SFP SFP level level 2 23 23 feet (151 (151 6)

'6") above above fuel fuel (4(4 pts) pts) --- 0-4 0-4 RED RED 47 47 2.

2. AA Tm Trn SFP SFP Cooling Cooling 55 ORANGE ORANGE 47 47 3.

3. BB Tm SFP Cooling Trn SFP Cooling 66 YELLOW YELLOW 47 47 44 22 SFP Makeup 2 SFP Makeup Sources (RWST, DW, Sources (RWST, OW, RMW RMW to Blender, Boric to Blender, Boric --- 77 GREEN GREEN Acid to Blender, Acid to Blender, RHT RHT to transfer canal to transfer canal with with weir gate removed) weir gate removed)

SFP SFP Subtotal Subtotal Page Page 77 of of 18 18 Version 36.0 Version 36.0

11/13/09 12:03:44 11113/0912:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 1I Figure 22 Figure Yellow/Orange Condition Yellow/Orange Condition Signs Signs Required Required for for Single Single Train Train Availability Availability

1. f required by step IF step 4.6, THEN place caution caution signs signs at applicable location location specified specified in for Unit 11 or Table 2 for or Table Table 33 for Unit Unit 2.

2.

2.

2. Signs should be worded Signs should worded similar similar to to the following:

following:

TRAIN OUTAGE IN PROGRESS NO WORK IS TO BE DONE ON THE TRAIN CALL EXT.

C&LEXT.

3. Complete Table 2 or 3 to document the review of posting requirements.

3.1 3.J Mark as N/A 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.

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

condition.

Reactivity Orange Condition Contingency Actions for Entry Reactivity 1.

1. Voluntary entry into a Reactivity Orange condition is not anticipated.

Reactivity Yellow Condition Contingency Actions for Entry 1.

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.

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or Yellow condition.

Core Cooling Core Orange Condition Cooling Orange Condition Contingency Contingency Actions Actions for for Entry Entry NOTE: entry into a core cooling Orange condition is not normally foreseen Voluntary entry foreseen for evolutions evolutions other than Mid LoopLoop Operations or other reduced inventory down for evolutions (e.g. drain down for reactor vessel head lift). Under certain plant conditions with time to saturation ~ 30 min.,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 ofFNP-I-UOP-4.3 of FNP-1-UOP-4.3 OR QE FNP-2-UOP-4.3, FNP-2-UOP-4.3, MID LOOP OPERATIONS, OPERATIONS, Compensatory measures in Appendix 3 of have been met, including the Mid-Loop Compensatory FNP-l-UOP-4.l OR FNP-2-UOP-4.1, FNP-I-UOP-4.1 FNP-2-UOP-4.1, CONTROLLING CONTROLLING PROCEDUREPROCEDURE FOR REFUELING.

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 compensatory FNP-1-UOP-4.11 OR FNP-2-UOP-4.1, Appendix 33 of FNP-I-UOP-4. FNP-2-UOP-4.1, CONTROLLING CONTROLLING PROCEDURE PROCEDURE REFUELING, have been met. These same contingency actions are applicable for FOR REFUELING, 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

< 23 feet (142l)

(142' 1") above the fuel.

Page Page 10 of 18 10 of 18 Version 36.0 Version 36.0

11/13/09 12:03:44 11113/0912:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 1I TABLE TABLE 1I Contingency Actions Contingency Actions Required Required for for Voluntary Voluntary Entry Entry toto aa Shutdown Shutdown Safety Safety Assessment Assessment Orange or Orange or Yellow Yellow condition.

condition.

Power Availability Orange Power Orange Condition Condition Contingency Contingency Actions Actions For For Entry Entry 1.

1. Verify RCS level ~ 126' 126 6"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 I1 or Unit 2 F OR ORG 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 BATP BATP TP if a BA TP is required as part of the boration flow path
• An operable RWST TO CHG PUMP SUCT MOV if the RWST is part of the boration flow path
• An operable RHR, CCW, and SW Pump

4. IF the head is on the reactor vessel, THEN at least one PRZR PORV is operable with iF 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 EMEM supervisory supervisory personnel personnel of AC power conditions and requirements and direct their personnel (including appropriate Williams and EFS personnel) be briefed on these these conditions and and requirements.

7.

7. Install Caution Install Caution Tags Tags or place barricades or place as appropriate barricades as appropriate toto identify identify components components such such as as ESF bus ESF bus feeder breaker, breaker, DGs, DGs, DG output breakers DG output breakers andand bus bus tie tie breakers, breakers, and and startup startup transformer associated associated with the ESF with the ESF bus be maintained bus to be maintained operable.

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44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 1I TABLE 1I TABLE Contingency Actions Contingency Actions Required Required for for Voluntary Voluntary Entry Entry to to aa Shutdown Shutdown Safety Safety Assessment Assessment Orange or Orange or Yellow condition.

Yellow condition.

Power Availability Yellow Power Condition Contingency Yellow Condition Contingency Actions Actions For For Entry I.

1. level 126' Verify RCS level;::: 126 6" 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 1I or Unit 2 F OR G 4160V 41 60V Bus is maintained with:

• An offsite power feed through its associated startup transformer.
• Its associated DG(s) operable
• An operable charging pump in the boration flow path
• An operable BABATP BATP TP if a BA TP is required as part of the boration flow path
• An operable RWST TO CHG PUMP SUCT MOV if the RWST is part of the boration flow path
• An operable RHR, CCW, and SW Pump

4. IF the head is on the reactor vessel, THEN at least one PRZR PORV is operable with backup nitrogen available for use in feed and spill cooling in the event that RHR is lost.

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 power conditions and requirements and direct their personnel (including (including appropriate Williams and EFS personnel) be briefed on these conditions and requirements.

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11/13/09 12:03:44 11113/0912:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 1I TABLE 1I TABLE Contingency Actions Required for Voluntary Entry to Contingency Actions Required for Voluntary Entry to aa Shutdown Shutdown Safety Safety Assessment Assessment Orange or Yellow Orange or Yellow condition.

condition.

Containment Orange Containment Orange Condition Condition Contingency Contingency Actions For For Entry 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 of FNP-1-UOP-4.3 OR Q FNP-2-UOP-4.3, MID LOOP OPERATIONS, have been met.

Containment Yellow Condition Contingency Actions For Entry I.

1. Not applicable.

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

condition.

Inventory Orange Inventory Orange Condition Condition Contingency Contingency Actions Actions For For Entry Entry 1.

1. Voluntary entry into an Inventory Orange condition is not anticipated.

Inventory Yellow Condition Contingency Actions For Entry 1.

I. Ensure both trains ofRHR of RHR are operable before reducing refueling cavity level to <<23 23 feet above fuel.

2. If entry is due to Mid Loop Operations, THEN based on the unit outage, ensure the IF FNP-1-UOP-4.3 OR FNP-2-UOP-4.3, requirements of FNP-I-UOP-4.3 FNP-2-UOP-4.3, have been met.

3. Specifications before removing RHR or HHSI systems Refer to applicable Technical Specifications from service.

Page Page 14 14 of of 18 18 Version Version 36.0 36.0

11/13/09 12:03 11/13/09 12:03:44

44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 11 TABLE 11 TABLE Contingency Actions Required for Voluntary Contingency Actions Required for Voluntary Entry Entry to Shutdown Safety to aa Shutdown Safety Assessment Assessment Orange or Orange or Yellow condition.

Yellow condition.

RCS Integrity RCS integrity Orange Orange Condition Condition Contingency Contingency Actions Actions ForFor Entry Entry 1.1. IF entry isis due IF entry due to to Mid Mid Loop Loop Operations, Operations, THEN THEN basedbased on on the the unit unit outage outage ensure ensure the the requirements of of FNP-I-UOP-4.3 FNP-1-UOP-4.3 OROR FNP-2-UOP-4.3, FNP-2UOP-4.3, MID LOOP OPERATIONS,OPERATIONS, have been met.

met.

2.

2. WHEN SG cold leg manways are to be opened OR cold leg nozzle nozzle dams are to be removed, THEN verify that at least one hot leg manway, diaphragm, and nozzle dam has been previously removed.

integrity Yellow Condition Contingency Actions For Entry RCS Integrity I.

1. IF entry is due to Mid Loop Operations, THEN based on the unit outage ensure the 11 of FNP-1-UOP-4.3 OR FNP-2-UOP-4.3, requirements ofFNP-I-UOP-4.3 FNP-2-UOP-4.3, MID LOOP OPERATIONS, OPERATIONS, have been met.

2. WHEN SG cold leg manways are to be opened Q 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 Page 1515 of of 1818 Version 36.0 Version 36.0

11/13/09 12:03:44 11113/0912:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX 1I APPENDIX TABLE 1I TABLE Contingency Actions Contingency Actions Required Required for for Voluntary Voluntary Entry Entry to Shutdown Safety to aa Shutdown Safety Assessment Assessment Orange condition.

Yellow condition.

or Yellow Orange or Spent Fuel Spent Fuel Cooling Cooling Orange Condition Contingency Orange Condition Contingency Actions Actions for for Entry Entry 1.

1. Voluntary entry into an Orange condition is not anticipated.

Spent Fuel Cooling Yellow Condition Contingency Actions for Entry I.

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 Page 16 16 of of 18 18 Version 36.0 Version 36.0

11/13/09 12:03:44 11113/0912:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 1I TABLE 22 TABLE Protected Train Protected Train Postings Postings Unit Unit 1I Components Components Sign Sign Posted Posted Sign Sign Removed Removed Initials Initials Initials Initials Charging Pump Charging Pump lA I A (B,C)

(B,C)

RHR Pump RHR Pump lAIA (B)

(B)

CCW Pump CCW Pump 1AIA (B,C)

(B,C)

BATP 1A(B}

BATP 1A (B)

Generator 1-2A Diesel Generator 1-2A (1 (IC, 2C, 1IB, C, 2C, B, 2B)

SFP Cooling lA IA 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 IA (B, C, D, E)

SW Valve Boxes Start Up Transformers 1I A, or 1I B Other Page 17 of Page 17 of 18 18 Version 36.0 Version 36.0

11/13/09 12:03:44 11113/09 12:03:44 FNP-0-UOP-4.0 FNP-0-UOP-4.0 APPENDIX APPENDIX 1I TABLE 33 TABLE Protected Train Protected Train Postings Postings Unit Unit 22 Components Components Sign Posted Sign Posted Sign Sign Removed Removed Initials Initials Initials Initials Charging Pump 2 (B,C)

Charging (B,C)

RFIR Pump 2 (B)

RHR (B)

CCW Pump 2 (B,C)

BATP 2 (B) 1-2A (1 Diesel Generator 1-2A (IC, 2B))

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 Page 18of18 18 of 18 Version 36.0 Version 36.0

FNP HL FNP HLT-33 T-33 ADMIN Page Page 11 of 77 A.2.1.A Equipment Control ADMIN -OOlA4.11-001A4.11- RO & & SRO HLT33-A.2.

HL 1 .A T33-A.2.1.A TITLE: Perfonn TITLE: Perform A Shutdown Shutdown Margin Calculation in modes 1I & & 2.

PROGRAM APPLICABLE: SOT SOCT OLT~

OLT X LOCT __

LOCT___

ACCEPTABLE EVALUATION METHOD: ~ X PERFORM SIMULATE DISCUSS EVALUATION EV ALUA TION LOCATION: SIMULATOR SIMULA TOR CONTROL ROOM --.lL X CLASSROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: N/A ALTERNATE AL TERNA TE PATH TIME CRITICAL PRA PRA______

JPM DIRECTIONS:

1. Initiation of task may be in group setting; evaluation perfonned I. performed individually upon completion of form.

the task by reviewing the completed fonn.

2. Provide the examinee with the required materials to perform this JPM.

TASK STANDARD: Required for successful completion of this JPM:

• Determine if Adequate Shutdown Margin exists while in Mode 1, using STP-29.5.

Detennine Examinee:

Overall JPM Performance: Satisfactory 0 Unsatisfactory 0D Evaluator Comments (attach additional sheets if necessary)

EXAMINER: _ _ _ _ _ _ _ _ __

Developer H. Fitzwater I 10/28/09 I NRC Approval I SEE NUREG 1021 1021 FORM ES-301-3

FNP HL FNP HLT-33 ADMIN T-33 ADMIN A.2.1 .A A.2.1.A Page Page 22 ofof 77 CONDITIONS CONDITIONS When II tell When tell you you to begin, you to begin, you are are to to Determine Determine if if Shutdown Shutdown Margin Margin isis adequate adequate using using STP-29.5, STP-29.5, SHUTDOWN MARGIN SHUTDOWN MARGIN CALCULATION CALCULATION IN MODES 11 AND IN MODES AND 22 (TAVG (TAVG 2: 547°F),

547°F), for for Unit Unit 1.

1. The The conditions under which conditions under which this this task task is is to to be be perfonned performed are:

are:

a. Unit 1I is is stable stable at 90% with with the ramp on hold

b. Bank D Bank D indicates indicates 192 192 by Group Demand.

by Group Demand.

c.

c. Seven of Seven of the the Bank Bank D rods (H2, (H2, B8, H 14, F6, FlO, K H14, 10, K6) are K10, are atat 192 192 steps steps by D RPI.

DRPI.

d. Rod P8, in in the D bank, has been detennined determined to be stuck.

e. Rod P8 is at 162 steps by DRPI.

f. All other rods are at 229 steps.

g. Core bumup burnup is 9,800 MWD/MTU bumup. burnup.

h. FNP-1-STP-29.5, SHUTDOWN MARGIN CALCULATION IN MODES 1I AND 2 (TA FNP-I-STP-29.5, (TAVGVG ~

547°F), initial conditions are satisfied.

i.

1. The Shift Supervisor has directed you to complete FNP-I-STP-29.5 FNP-1-STP-29.5 starting at step 5.1.

INITIATING CUE: You may begin."

"You begin.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME NOTE: Elements 1I through 13 are evaluated by comparing the completed Calculation page to the values ranges and ran es of each element. The acceacceptable table res onses are ALSO listed on the calculation KEY.

responses I. Step A.1:

1. A.I: Document Core Burnup 1)

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

2. Step A.2: Document Power Level 2) Value entered: 90 % entered S I/ U U

FNP HL FNP HLT-33 ADMIN T-33 ADMIN A.2.1 .A A.2.1.A Page Page 33 of of 77 EVALUATI EVALUATION CHECKLIST ON CHECKLIST RESULTS:

RESULTS:

ELEMENTS:

ELEMENTS: STANDARDS:

STANDARDS: (CIRCLE)

(CIRCLE)

3. Step A.3;

3. Step Determine penalty A.3: Determine penalty steps steps for for Banks Banks 3) Value

3) Value entered; entered: ZERO ZERO (0) (0) SS/Uf U below RIL.

below RIL. RNG: NONE)

(RNG: NONE) a) Using COLR a) Using COLR figure figure 11 determines determines RIL RIL (a). Determines (a). Determines RILRIL from from COLR COLR for 90% power level.

for 90% power level. ** CB Df RIL = 167 CBD/RIL=1 (165-67(165-170) 170) from from COLR.

COLR.

• CBC f RIL = FULL CBC/RIL=F ULLOUT OUT (or (or 229).

229).

b) Gathers b) data from Gathers data from Conditions Conditions page page (b). Documents given (b). Documents given Demand Demand positions

• CB Df D/ Demand 192.192.
• All others: Full All others; Full out out (or (or c) c) Determines penalty stepssteps per bank. 229)

(c). Calculates difference

• All values: 0 (RNG; (RNG: NONE)
• • 4. Step A.4: Determine number of penalty steps 4) Value entered: 5 f U SS/U for RODS below RIL (RNG; (RNG: 3-8) a) Determines stuck rod in CBD, Determines CBD RIL.R1L. (a). Determines RIL from COLR
• P8 -7 CB Df RIL=167 P8-CBD/RlL = 167 (Range; (Range: 165-170) from b) Documents given Data for rod P-8 COLR.

(b). Documents given data

i. Rod # -7 P8 @ 162 I. Rod#-P8@16 2 c) Calculates difference (c). Calculates difference (c).

(RIL - DRPI) = 5 (RNG:

(RNG; 3-8)

• 5. Step B.1:B.1; Determine Rod Worth for all 5) Value entered: 6268 pcm.

5) S f U s/U control and shutdown bandsbands at Zero steps (range; NONE)

(range: NONE) using given power and burnup:

given power bumup:

Uses Curve a) Uses Curve 77 pg 11 for 90%

77 pg 90% power power and 1 0000MWD and 10000MWD 6.

6. StepStep B.2:

B.2: Calculate penalty value Calculate penalty value ofof rod rod banks banks 6) Value

6) Value entered entered of of 00 (zero)

(zero) pcm pcm S f U S/U

• 7.7. Step B.3:

Step B.3: Calculate Calculate penalty penalty value value ofof individual individual 7) Value

7) Value entered entered of of 50 50 pcm pcm S f UU SI rods rods (range; 30-80)

(range: 30-80)

FNP HLT-33 FNP ADMIN HLT-33 ADMIN A.2.1 .A A.2.1.A Page Page 44 of of 77 EVALUATION CHECKLIST EVALUATION CHECKLIST RESULTS:

RESULTS:

ELEMENTS:

ELEMENTS: STANDARDS:

STANDARDS: (CIRCLE)

(CIRCLE)

• • 8. Step

8. Step B.4.a; Determine most reactive Rod B.4.a; Determine 8) Value entered

8) entered of of 1406 1406 pcm pcm SS I/ U worth (range: NONE)

(range: NONE)

From Curve 77 pg (a). From pg 22 for for ::::

I 0000MWD.

10000MWD.

• • 9. Step B.4.b; Calculate rod worth of 9) Value entered of3515 of 3515 S I U stuck/untrippable rod stuckluntrippable (RNG: 3515- 3516)

(a). # of stuck: 11 rod (b). B.4.a: 1406.

1406.

(+11 I/ -0) value for various

(+

rounding technique effects)

• • 10. Step B.5; Calculate penalized rod worth 10)

10) Value entered of: S I/ U

(-)

(-) 2432.7 NOTE: NEG (-) (-) SIGN IS IMPORTANT IMPOR TANT FOR THIS CALCULA TIONlEvaluation TION/Evaluation (RNG: (-)2403 to (-) (-) 2451 2451))

Transpose data from other steps:

B.l: 6268 (a). B.I: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. 11) Value entered of: SS I UU conditions 1634 pcm 1634 (RNG: NONE)

(a). From Curve 78 for for::::

0000MWD.

110000MWD.

FNP HL FNP HLT-33 ADMIN T-33 ADMIN A.2.1 .A A.2.1.A Page Page 55 ofof 77 EVALUATION CHECKLIST EVALUATION CHECKLIST RESULTS:

RESULTS:

ELEMENTS:

ELEMENTS: STANDARDS:

STANDARDS: (CIRCLE)

(CIRCLE)

• • 12. Step

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

12) Value entered Value entered of:of: SS // U U Reactivity Reactivity (-) 748.7

(-) 748.7 (RNG:

(RNG: -718 -718 toto -767)

-767)

NOTE: NEG NOTE: NEG (-) (-) SIGN SIGN IS IS IMPORTANT FOR THIS IMPORTANT THIS CALCULA TION/Evaluation CALCULATIONlEvaluation (a). Transpose data:

i.1. B.5: (-)

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

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

13) Value entered of: S / U 1021.3

(+) 1021.3

(+)

RNG: 1003 to 1051)

((RNG:

NOTE: POS (+) (+) SIGN IS IMPORTANT IMPOR TANT FOR THIS CALCULA TIONlEvaluation TION/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 performed if initiated as a group/classroom setting, therefore it may be necessary to provide the following cue during group/classroom review/evaluation of work sheet:

review/evaluation Is the SDM adequate?"

CUE: "Is adequate?

• 14. Step B.1O:

B.I0: Identifies Need to Emergency 14) Notifies Shift Supervisor of SS / U U Borate need to Emergency Borate.

OR OR OR Notifies SS that SDM is NOT adequate (does Reports SDM is NOT not meet acceptance criteria),

criteria). adequate.

15. completes task: 15) Completes sign off. SS / UU a) Signs and dates Calculation Sheet (a). Signs and dates form b) Initials step b) step 5.1 5.1 (b).lnitials step 5.1 (b ).Initials step 5.1 of of procedure.

c) Asks for verification verification of of calculation I TERMINATE After calculation of Excess Shutdown LIMINATE Shutdown Margin AND element element 14 14 completed.

completed.

STOP TIME STOP TIME

FNP HLT-33 ADMIN FNP HLT-33 ADMIN A.2.1 .A A.2.1.A Page Page 66 of of 77 CRITICAL ELEMENTS  : Critical CRITICAL ELEMENTS: Critical Elements areElements are denoted denoted with with an an asterisk (*)

asterisk (*) before before the the element element number.

number.

GENERAL

REFERENCES:

GENERAL

REFERENCES:

I. FNP-I-STP-29.5,

1. FNP-I-STP-29.5, VER4.0 VER4.O

2. KA:

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

EQUIPMENT:

1.

1. FNP-I-STP-29.5, ver FNP-I-STP-29.5, ver4.O 4.0

2. PCB-VOLI-CRV77, Cycle 23 rev 88 PCB-VOLl-CRV77,

3. PCB-VOLI-CRV78, Cycle 23 PCB-VOLl-CRV78, rev 8 23 rev 4.

4. Unit 1, COLR for 1, COLR for FNP Unitl Unit I Cycle Cycle 23, 23, Rev 00 Figure 1.

1.

5.

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.

15 CRITICAL - Task Objective; Identification that Acceptance Criteria NOT met and/or Emergency boration IS required to ensure corrective action is initiated and compliance with T.S. is restored.

COMMENTS:

COMMENTS:

KEY A.

A. PRESENT CONDITIONS PRESENT CONDITIONS A.1 A.I Core 19800 Burnup 19_80_0_

Core Bumup .... ....IMWD/MTU IMWD/MTU A.2 A.2 Level.

Power Level.

Power 119090 II % °° A.3 A.3 Determine number of penalty steps for ROD BANKS below RIL.

(Use COLR or convert the RIL RIL computer reading from % to steps)

A.3.a Record data in in table ROD BANK RIL BANKRIL BANK STEPS BELOW BANKS HEIGHT DEMAND RIL ,....-

CBA FULL OUT Full Out (229) 0 CBB 11l1 RT IT T I nT flTTT TT Full Out (229) 0 CBC Full Out(229) jFull Out(229)rI - - Full Out (229) 0 CBD 167 (166-170) I - - 0 j 192 SDA FULL FULL UUT OUT Full Out (229) 0 SDB FULL OUT Full Out (229) 0 TOTAL STEPS BELOW RIL :LII I... _ _ _ _

0 II :

---..I RANGE for CBD RIL:

LO: Readability of COLR RIL curve may allow allow as low as 165 steps; although this is <than

< than the curve limit of 166.9, 166.9, if calculated. The assumptions within the curve development provides for this readability error.

HI:

HI: conservatism conservatism allowed by P&L 4.1 may byP&L4.1 be instituted and maybe and a value of up to value of 170 may be selected since the specific value between the Y-axis 170 steps may increments may not be calculated.

Page Page 1I of of33 Revision 44 Revision

KEY A.4 uetermine riuniber 01 penaity steps ror 1ULTh oeiow iciL wnicn were not countea in A.i (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 A.4.a Record data inin table table ROD NUMBER ROD NUMBER I RIL POSITION I DRPI RIL POSITION POSITION I DIFFERENCE DRPI POSITION DIFFERENCE

~ P8 P8 167 167 (+3,-2)

(+3,-2) 162 162 55 (3-8)

(3-8) ~

TOTAL STEPS BELOW RIL I155 (RANGE 3-8)

IL_1ANGE3-8)

L.._

I.

B. SHUTDOWN MARGIN NOTE: Write the values from Curves 77 & & 78 directly into the surveillance test.

The correct sign convention has been entered in the STP.

B. I B.l Rod worth for all control and shutdown banks at zero steps at Present Burnup (A. (A.l) Power Level

1) and Power Level (A.2).

(A.2). :I ~_~"'1-6-2-6-8-""lp:~-:

() 16268 I pcm i (Curve L __________ _

77 Page 1) 1 I L

B.2 B.2 Penalty value of rod banks banks below insertion limit:

o

[o (A.3.a)

(A.3.a) steps x 75 steps 75 pcm/step pcm/step =

=

B.3 B.3 Penalty Penalty value value ofof individual individual rods rods below below RIL RIL which which were were not not counted counted inin A.3 A.3 r--~;w.£...QIi:,~ RIL (1?rdc li1-vij1 RIL onon DRPI DRPI when when the the BANK BANK demand demand isis above above RIL)

RIL) 55 I r r------------

(RANGE (RANGE 3-8) s 1

3-8)__ s xx 10 pcm/step ==

10 pcm/step I_ _

(+)j I (+) 50 50 em:

cm (A.4.a)

(A.4.a) 138) ___ J (RNG 30-80) i Page 22 of Page of33 Revision 44 Revision

B.4 B.4 Stuck I/ Untrippable Stuck Untrippable Rod is (B.4.a is N/A and B.4.b (B.4.a N/A and Rod penalty:

B.4.b is penalty:

is zero zero if KEY if there there are are nono stuck/untrippable stuck/untrippable rods)

I rods)

B.4.a Worth of B.4.a from Curve of most reactive rod worth at at present burnup (A.1) (A.l) (-)J (_)j14061406 ipcm Ipcm from Curve 77 pg. pg. 2 B.4.b Calculate B.4.b Calculate worth worth of of Stuckluntrippable Stuckluntrippable rods rods

(( EJStuck!

1 xx() (-)~ 1406 I k 1.75]

1.75] +

+ [(_)1

[()

1406 1406 0 75] == (_) 3S1S xxO.75]

3515 range:

ran e 3S1S 3515 to 3S16 3516

( Stucki

(# (B.4.a) (B.4.a)

(B.4.a) 246 o

4 untripPj ii untripp osto r,:,24QO~5)tq~~~1] ..*.. . ....... + -1054.5 to -1055]

(( -1054.5to -1055] =:

I  :.;X[~5~,~9It35161

[35150R3516J B.5 Penalized rcfrT'~"""~~mm~.,.;MIMT!"""""""'~~I"IT'I"i~---I rdu WUI LII UH.IU11H LUIJUHL1LppauI IUU, misaligned rods, rods below the insertion limit, and uncertainty:

50 I ...-------,- .,

r--"'~~-.......Lrl,;;;(--;;J,._).!:16=2:::::68:::::::::::::!.I..:.+~lo:;:::!.1 I El ~+..L,~~~0~-~80.;...)~(_) ~~~~O) xx 0.9 3515

[(_) +

+ (30-80) (+1, ..Oj 1I

( )

(-) 2432.7 range:

(-)

1 ( ) -2403 to -2451 to-2451 In:

LL_ _ "'___ _ _ _ H268+$(}+3~15)"'O.97'~10~;~:I;)\<}.>>)ri>r~(;;).(;

l6268+80+3515]*0.9 = 2405.7 *.,) *. l.. (B.4.

(B.4.b) b)

• 09 = 2403.9 (Round down to 2403)*LO

[-6268+80+3517] .~().~.*724~3.~*tJt~W!~qo~p~~40~1*:LO

£-(j26.8+8.0+35)7J

[_6268+30+3515]*0.9 = *. 2450~!@()uti(f:UP)tO~~451)*(hi)

H268+3(}+3515]"'(}19.;,;,* 2450.7 (Round up to 2451) (hi) l-6268+30+35 171 *0.9= ...,9.;..b_*.~

• 4......8....9_*". . . . . . . . ................H.;..i~i...

2448.9 L.[_-6_26_8_+_30_+_.35.;..1_7_l*_O ..... *******....

• • • ..**.... )...........--Jl Burnup (A.

nd Burnup (A. 11)) 1634 (Curve 78). (-)

() 1 lpcm pcm B.7 Void Collapse Defect. (+)

(+) 50 pcm B .8 B.8 Available Shutdown Reactivity:

(-) 748.7

(-) - - 1

)[24327

(()1-2432.7 L-

[_ (_)---1.1_

(_) 11634163_4 _ . . 1 - +

I + 50 Range:

-719 to -7670-767.0 pcmlI pcnl 1

(B.5) (B.6) (B.7)

B.9 Shutdown Margin in excess of required Shutdown Margin (B.8 - Required SDM from the COLR):

r - - - - - - - - - - -I 1-748.7 1-748.7 i(+/-)102131:

1 (+) 1021.3 1 a~,==~L...... pcm () - (-) 1770 1770 pcm 1 ( Range: 1003 1003 ~m m 1 (B.8) Required SDM to _

tolOSi 1..._ ...... IOS1

_ __ I L...________

from the the COLR CO LR B.

B.1O 10 If IfB.9 B.9 is positive, THEN THEN emergency emergency borate per FNP-l-AOP-27.0, FNP-I-AOP-27.0, EMERGENCY

...--~~-~-

EmergencyB~ration Emergency Boration BORATION, to establish the required shutdown margin otherwise Shutdown IS required .

ISrequired . Margin is adequate for the Present plant condition. condition.

May also state DATE--

DA TE-- EIenent Element 15-if IS-if Signed-- element Signed-- element 15-I S- if if assumes/states May.also state that that aa Per forme d by.

assumes/states assumes/states Performed by: ____Emerg

_ Emerg Boration Boration completed completed Rx trip Rx tripmaymay he be rrnt, warranted (P&L43). emergency emergency boration boration completed completed Verified by:

Verified by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Page 33 of Page of3 3 Revision 44 Revision

Westinghouse Proprietary Westinghouse Class 22 Proprietary Class PCB-l-VOU-CRV77 PCB-1-VOL1-CRV77 UNIT 11 CYCLE UNIT CYCLE 23 23 CURVE CURVE 77 77 Ij REV.~

REV.

KEY I

~~

APPROVED:

APPROVED: <?(~...e & Iv,.-

) pry".., C'7r'n~'"

ENGINEERING SUPPORT ENGINEERING SUPPORT MANAGER MANAGER DATE DATE ARI-l Rod ARI-1 Rod Worth Worth (pcm) for Shutdown Margin Calculations BumupRange Burnup Range Power Level Power Level (%)

(%)

(MWDIMTU)

(MWD/MTU) 00 10 10 20 20 30 30 40 50 50 60 60 70 80 80 90 100 100

=:;150 150 4587 4710 4831 5071 5071 5311 5483 5655 5655 5792 5792 5927 6162 6397

> 150 150 =:;1000 1000 4667 4801 4935 5180 5425 5594 5594 5762 5762 5905 6048 6285 6523

> 1000 1000 =:;2000 2000 4717 4867 5017 5267 5517 5680 5844 5844 5995 6145 6384 6623

> 2000

>2000 =:;3000 3000 4755 4909 5063 5320 5578 5740 5902 6052 6201 6442 6683

>3000 =:;4000 S 4000 4818 4975 5131 5396 5660 5814 5969 6113 6257 6483 6708

>4000

> 4000 5=:;5000 5000 4767 4920 5072 5346 5619 5778 5938 6073 6208 6439 6670

> 5000

> =:;6000 6000 4717 4865 5013 5296 5579 5743 5906 6033 6159 6395 6631

> 6000

> =:;7000 7000 4689 4827 4965 5254 5542 5714 5885 6001 6118 6355 6593

> 7000 =:;8000 5 8000 4660 4788 4916 5211 5506 5685 5864 51 Element #6 finent 6316 6555

.> 800.0

>8000 =:;c;)OQO 59000 . 4646

.464.6. 4:7'6.5 4765 .4~84 4884 5182 5480 5669 5857 54 5j 6292 -

6531

=:;10000 4852 4632 4742 5154 5652 5850 5939

+~~}~

>9000

> 9000 10000 5455 6028 6268 6507 6028

>10000 =:;11000 511000 4622 4725 4828 5129 5431 5431 5641' 5641 5850 5933 6016 6253 1----6490 h 6490

>11000 =:;12000 512000 4612 4707 4803 5105 5408 5629 5850 5927 6004 6239 6473

>12000 =:;13000 513000 4617 4706 4795 5096 5398 5631 5865 5937 6010 6242 6475

>13000 =:;14000 514000 4621 4704 4787 5087 5387 5633 5879 5947 6015 6245 6476

>14000 =:;15000 515000 4631 4709 4787 5086 5385 5642 5900 5964 6028 6256 6485

>15000 =:;16000 16000 4641 4714 4787 5085 5382 5652 5921 5981 6041 6267 6493

>16000 =:;17000 517000 4662 4731 4800 5096 5391 5669 5947 6004 6062 6286 6510

>17000 =:;18000 518000 4682 4748 4813 5107 5400 5687 5973 6028 6083 6304 6526

>18000 =:;19000 519000 4709 4771 4833 5125 5418 5710 6002 6056 6109 6328 6547

>19000 =:;20000 20000 4735 4794 4852 5144 5435 5734 6032 6083 6135 6351 6568

>20000 =:;20885 520885 4760 4818 4876 5165 5454 5759 6063 6112 6161 6377 6592 Notes:

1.

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

RIL.

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

STP.

3.

3. ARI-lARI4 isis defined defined as as All All Rods Rods InIn --less

-- less the the most most reactive reactive rod. The SDM rod. The calculation requires SDM calculation that one requires that one rod rod be assumed be assumed stuck.

stuck. Therefore, Therefore, use use the the data data directly directly from from the the table table above above whenwhen there there are not any are not any known stuck rods.

known stuck rods.

Page Page 11 of of 22

Proprietary Class 2 Westinghouse Proprietary PCB-I-VOLl-CRV77 PCB-1-VOL1-CRv77 UNIT 11 CYCLE 23 CURVE 77 Control Rod Worth for SDM Calculations KEY REV.

APPROVED: -

0/~ 4 A': 1 f-bf lor cr ptrtfYl f1'-;,jW

~ LI_/c c ENGINEERING SUPPORT MANAGER DATE Worth of Most Reactive Rod (pern) (pcm) for Shutdown Margin Calculations Burnup Range Power Level (MWDIMTU)

(MWD/MTU) 0% to 100%

150 150 658

> 150  ::;;1000 1000 676

> 1000

>1000  ::;;2000 2000 732

> 2000

>2000 3000

3000 781

>3000 4000

4000 889

> 4000

>4000 5000

5000 1024

> 5000  ::;;6000 6000 1160

> 6000 7000

7000 1232

> 7000 8000

<8000 1304 Ielement #9 :iI- > 8000 9000

9000 1355

> 9000 10000

10000 1406

>10000  ::;;11000 11000 1450

>11000 12000

12000 1494

>12000 13000

13000 1528

>13000  ::;;14000 14000 1561

>14000 15000

15000 1592

>15000  ::;;16000 16000 1623

>16000 17000

17000 1653

>17000 18000

18000 1684

>18000 19000

19000 1713

>19000  ::;;20000 20000 1741

>20000 ::;;20885 20885 1767 Notes:

1.

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

3.

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

4. For multiple stuck rods, the ARI-1 ARl-l value on Page 1 1 of this curve should be reduced by by the following calculation:

1.75] ++ [WSR xx 0.75]

[KUR x WSR x 1.75]

where KUR == Number of known untrippable rods (does not include rod assumed stuck stuck in ARI-1 ARl-l table) and WSR == Worst stuck rod (i.e. most reactive rod)

Page 22of2 Page of 2

Westinghouse Westinghouse Proprietary Class 22 Proprietary Class PCB-1-VOL1-CRV78 PCB-l-VOLI-CRV78 UNIT UNIT 11 CYCLE CYCLE 23 CURVE 78 23 CURVE 78 REV.

APPROVED:

APPROVED: ~<t" (fL""" ~

ENGINEERING SUPPORT MANAGER MANAGER DATE Power Defect Defect (pcm) for Shutdown Shutdown Margin Margin Calculations Burnup Range Burnup Power Power Level Level (%)(%)

(MWDIMTU)

(MWDiMTU) 00 10 10 20 20 30 30 40 50 50 60 70 70 80 80 90 90 100 100 S 150 150 00 361 537 717 898 958 1019 1119 1219 1326 1432

>150 150 s1000 1000 00 351 522 701 879 943 1006 1006 1106 1206 1206 1307 1409 1409

>1000

> 1000 s2000 2000 00 330 495 667 839 903 967 1068 1169 1265 1361

>2000

> 2000 s3000 3000 00 317 476 647 818 879 941 1041 1142 1237 1332

>3000

> 3000 s4000 4000 00 326 489 664 839 901 964 1062 1161 1261 1360

>4000

> 4000 s 5000 0 344 514 697 879 942 1004 1103 1202 1306 1410

> 5000

>5000 s6000 6000 0 362 539 729 919 982 1045 1045 1144 1242 1242 1351 1459

> 6000

>6000 s7000 7000 0 388 576 774 972 1037 1103 1202 1301 1416 1531

>7000

> 7000 s8000 8000 0 414 613 818 1024 1092 1160 1260 1360 1481 1603 8000

... > 8(100..

>9000 9000 .....

s 90(10 s10000 10000 0

~Q

.00 ......... . . . . . 440 466 651

................. 1~~I:

690 863 907 1074 1124 1147 1202 1220...*...

1280 1391 1503 1634 11 Element #12 I 1558 entii] 1684 1765

>10000 s11000 11000 0 492 728 950 1173 1258 1344 1461 1579 1717 1854

>11000 s12000 12000 0 518 766 994 1222 1315 1408 1531 1655 1800 1944

>12000 s13000 13000 0 543 804 1035 1267 1369 1471 1603 1734 1884 2034

>13000 s14000 14000 0 567 841 1077 1313 1424 1535 1674 1813 1968 2123

>14000 s15000 15000 0 589 875 1115 1356 1477 1597 1744 1890 2054 2217

>15000 s16000 16000 0 611 908 1153 1399 1529 1660 1813 1967 2139 2310

>16000 s17000 17000 0 633 940 1189 1438 1578 1718 1882 2046 2223 2400

>17000 s18000 18000 0 654 971 1225 1478 1627 1777 1951 2125 2307 2489

>18000 s19000 19000 0 673 1001 1259 1516 1677 1837 2020 2203 2392 2582

>19000 s20000 20000 0 692 1031 1293 1554 1726 1897 2089 2280 2477 2674

>20000 s20885 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 1.

entered as a positive number. Enter the above numbers directly into the STP. Si]?.

COLR for FNP Unit 11 Cycle 23 Revision 0 Page Pacie 10 of 13 Figure 1 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive IElements 4 Elements 4 & 5 5 I 225 J;!'

I....

I I I I I I

(.552,225) m I'

200 o-J;!' (1,187) _

175 ,/

I;' ,/

I' I' Banke

'2C i;"

,/ I I I I I

==

~

150 II II-f.

"t:I 7

-c

.J::. .1' = (_1Jl. - 0.000 )(0.900 - 0.(70)+ 0.000 1.00 - 0.070

§: i;" =166.9 (rounded using 4 signticJnt digits)

Y

t Q. 125 I' => 167sfeps

.l!!

U)

!a- if not calculated and only read from graph I~

s:::

C (0, 114) then> 165 And < 170; Therefore Half the accuracy of the scale II' 00

=> 167.5 I' 0Cij

• i 100 00 I....

a. I.;'

olo: BankO s:::

C C\I IX!

"t:I 75 I....

00 IJ a:: II' 50 '-' .

II I I

,/

25

(.070,0) o0 " I I I I r 0.0 0.1 0.2 0.3 0.4 04 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, 0 D and a control bank tip-to-tip distance of 128 steps.

06/18/01 10:31 06/18/01 10 31 :04 04 FNP-I-STP-29.5 FNP-1-STP-29 5 April April 2] , 2000 21,2000 Revision Revision 44 FARLEY NUCLEAR FARLEY NUCLEAR PLANTPLANT SURVEILLANCE TEST SURVEILLANCE TEST PROCEDURE PROCEDURE FNP- I -STP-29.5 FNP-I-STP-29.5 S

A F

E E

T Y

MODES I AND 2 (TAVG SHUTDOWN MARGIN CALCULATION IN MODES] ~ 547°F)

R R

E L

A T

E D

PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use ALL Reference Use Information Use Infonnation Approved:

C. D. COLLINS Operations Manager Date Issued _4..:....-=27'---"'-00~

4-27-00 _ _ _ _ __

06/18/01 06/18/01 10:31:0410 31 04 FNP-l-STP-29.5 FNP-I-STP-29 5 FARLEY NUCLEAR FARLEY NUCLEAR PLANT PLANT SURVEILLANCE TEST SURVEILLANCE TEST REVIEW REVIEW SHEET SHEET SURVEILLANCE TEST SURVEILLANCE TEST NO.

NO. TECHNICAL SPECIFICA TECHNICAL SPECIFICATION nON REFERENCE REFERENCE FNP- I -STP-29.5 FNP-1-STP-29.5 TR 13.1.1; TR 13.1.1; LCOLCO 3.1.4; 3.1.4; LCO LCO 3.1.5; 3.1.5; LCO LCO 3.1.6 3.1.6 TITLE TITLE MODE(S)

MODE(S) REQUIRING REQUIRING TEST: TEST:

SHUTDOWN MARGIN SHUTDOWN MARGIN CALCULATION CALCULATION IN IN MODES MODES 1I AND AND 22 *,2*

11 *,2*

(TAVG ~ 547°F)

(TAVG 547°F) *See special

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

BY TEST PERFORMER)

PERFORMED BY PERFORMED DATE/TIME_________________________

DATE/TIME COMPONENT OR COMPONENT OR TRAIN TRAIN TESTED TESTED (if(if applicable) applicable)

ENTIRE STP

((j] ENTIRE STP PERFORMED FOR SURVEILLANCE

(()) FOR SURVEILLANCE CREDIT CREDIT

[]{] PARTIAL STP PERFORMED: ((1] NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL:

TEST COMPLETED: (()) Satisfactory [ ]j Unsatisfactory

(()) The following deficiencies occurred:

(()) Corrective action taken or initiated:

SHIFT FOREMAN REVIEW REVIEWED BY DATE

[ ] Procedure properly completed and satisfactory

[j

[ ] Comments:

[] Comments:

TECHNICAL GROUP GROUP-REACTOR ENG REVIEW REVIEW REVIEWED BY BY DATE

(( J] Satisfactory and Approved Satisfactory and

(( j] Comments:

Comments:

Revision Revision 44

06/18/01 10:31 06118/01 10:31:04

04 FNP-1-STP-29.5 FNP-1STP-29.5 TABLE OF TABLE OF CONTENTS CONTENTS Procedure Contains Procedure Contains Number of Number of Pages Pages Body ......................................................... 22 Body Shutdown Margin Shutdown Margin ..................................... 33 STRS ........................................................ 1I STRS Page Page 11 of of I1 Revision 44 Revision

06/18/01 10:31:04 06118/01 10 31 04 FNP-I-STP-29.5 FNP-1-STP-29 5 FARLEY NUCLEAR FARLEY NUCLEAR PLANT PLANT UNIT 1I UNIT SURVEILLANCE TEST SURVEILLANCE TEST PROCEDURE PROCEDURE STP-29.5 STP-29.5 SHUTDOWN MARGIN SHUTDOWN MARGIN CALCULATION CALCULATION IN IN MODES MODES 11 AND (TAVG ~ 547°F)

AND 22 (TAVG 547°F) 1.0 1.0 Purpose Purpose 1.1 The purpose of this procedure is to verify that the SHUTDOWN MARGIN is greater than the limits of of the Technical Requirements Manual Manual TR 13.1.1 13.1.1 as as directed by Technical Specifications Specifications in Modes 1I or 2:

.1 .1 1.1.1 One or more roderod(s) s) untrippable (LCO 3.1.4),

1.1.2 1.1.2 One or more roderod(s) 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 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 I1-98-498) 498)

HBF 3.2 547° F.

TAVG HBF HBF 33 3.3 TAVG +/-+/-

TAVG I1OF

° F of programmed value. (Needed for Power Defect to be accurate)

HBF HBF 3.4 The plant is in Mode 1 I or 22 with Keff ~ 1.

1.

HBF 3.5 3.5 Technical Technical Specifications required action action entered to verify verify SDM to bebe within within the limits provided in in the COLR Qj OR Shift Shift Supervisor desires to perform.

-I-Revision 44

06/18/01 10:31:04 06118/0110:31:04 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 IF necessary to emergency borate due to inadequate shutdown margin, margin. THEN consideration should be given to tripping the reactor and entering FNP-1-EEP-0, FNP- I -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 immediately..

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 44

06/18/01 10:31 06118101 10:31:04

04 FNP-I-STP-29.5 FNP-1-STP-29.5 SHUTDOWN MARGIN SHUTDOWN MARGIN IN IN MODES MODES 11 AND AND 22 A.

A. PRESENT CONDITIONS PRESENT CONDITIONS A.1 A.I Core Bumup Core Bumup _ _ _ MWDIMTUMWD/MTU A.2 Level.

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 BANK RIL BANKRIL BANK STEPS BELOW BANKS HEIGHT DEMAND RIL CBA FULL OUT CBB FULL OUT CBC CBD SDA FULL OUT SDB SOB FULL OUT TOTAL STEPS BELOW RIL i"- _ _ _ _ _ _ _ _ ..1 Page Page 11 of of 33 Revision 44 Revision

06/18/01 10:31 06118101 10 31 :04 04 FNP-I-STP-29.5 FNP-1-STP-29 5 A.4 AA Determine number Determine number of penalty steps of penalty steps for for RODS RODS below below RIL RIL which which were were not not counted counted in in A.3 A.3 (Rods below RIL (Rods below RIL onon DRPI DRPI when when the the BANK BANK demand demand isis above above RIL)RIL)

(Use COLR or (Use COLR or convert convert the the RIL RIL computer computer reading reading from from %  % toto steps) steps)

AA.a Record data A.4.a Record data in table in table ROD NUMBER ROD RIL POSITION RIL POSITION DRPI DRPI POSITION POSITION DIFFERENCE DIFFERENCE TOTAL STEPS BELOW RIL

.... _------- ... .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.

B.lI Rod worth for all control and shutdown banks at zero steps at r - - - - - - - - - - -I Burnup (A.

Present Bumup (A.l) (A.2)..

1) and Power Level (A.2) 1 (_)

() pcm 1 1 1 i (Curve 77 Page 1) 1 L __________ _

L B.2 Penalty value of rod banks below insertion limit:

_ _ _ steps x 75 pcm/step (A.3.a)

=  :

1 1 (+)_ _ _ _pcm 1 L __________ _1 L

B.3 Penalty value of individual rods below RIL whichwhich were not counted counted in A.3 (Rods below RIL on DRPI when the BANK BANK demand is above RIL) r------------

I1 (+) pcm:

pcm

_ _ _ steps x 10 10 pcm/step pcm/step =  !... (+)

___________ J (A.4.a)

(AA.a)

Page Page 22 of of33 Revision 44 Revision

06/18/01 10:31 06118/01 10:31:04 :04 FNP-1-STP-29.5 FNP-I-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/untrippabJe stuckluntrippable rods)

B.4.a Worth of most reactive rod worth at present burn burnup up (A. I ) (-)

(A.1) ()_ _ _ _pcm from Curve 77 pg. 2 Stuck/untrippable rods B.4.b Calculate worth of Stuckluntrippable

(( ()

x (-) x 1.75] + + [(-)

[() x 0.75] == ()

(-) _ _ _ pcm Stuck!

(# Stucki (B.4.a) (B.4.a) untrippable rods) (Most reactive (Most reactive rod worth) rod worth)

B.5 stuck!untrippable rods, Penalized rod worth considering stuckluntrippable misaligned rods, rods below the insertion limit, and uncertainty:

1 1

[(-) _ _ _ ++

[(-.L-) +

+ -- (-)

(-) ]1 x 0.9 to 1 ( )

L L __________ _

pcm 1 (B.1)

(B.I) (B.2) (B.3) (B.4.b)

B.6 Power Defect at Power Level (A.2) and Burnup (A. (A.1)

I)

(Curve 78). (-)

() _ _ _ _pcm B.7 Void Collapse Defect. 50 pcm

(+) _---'5o....=O'---_pcm B.8 Available A vailable Shutdown Reactivity:

1- - - - - - - - - - - ,.7

( ),----(-),---- +

()______ ()________ 50 I

!... ______ __ ~c~~ pcmi1 (B.5) (B.6) (B.7)

B.9 Shutdown Margin in excess of required Shutdown Margin (B.8 - Required SDM from the COLR):

r - - - - - - - - - - -I 0 ____ pcm - (-)

()___________ () 1770 pcm  : () 0) pcm 1 (B.8) Required SDM t (SDMExcess) I 1... __________ _

L..

fromtheCOLR from the CO LR B.10 B.IO If B.9 is positive, THEN emergency borate per FNP-l-AOP-27.0, FNP-I-AOP-27 .0, EMERGENCY BORA TION, to establish the required shutdown margin otherwise Shutdown BORATION, Margin is adequate for the Present plant condition.

Date:

Date:___________________ Performed by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Date:

Date:____________________ Verified by: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Page 33 of of33 Revision 4

Westinghous Westinghouse e Proprietary Class 22 Proprietary Class PCB-1-VOL 1-CRV77 PCB-l-VOLl-CRV77 UNIT 11 CYCLE UNIT CYCLE 23 CURVE 77 23 CURVE 77 Control Rod Control Rod Worth Worth for for SDM SDM Calculations Calculations REv.l REV.

APPROVED:: t')(~..e fd,

(<4; Iv,- P'Pl-n c'?r'no-APPROVED ENGINEERING ENGINEERI SUPPORT MANAGER NG SUPPORT MANAGER DATE DATE ARI-l Rod ARI-1 Rod Worth Worth (pcm)(pcm) for for Shutdown Shutdown MarginMargin Calculations Calculations Burnup Range Bumup Range Power Level Power Level (%)(%)

(MWDIMTU))

(MWDIMTU 00 10 10 20 20 30 30 40 40 50 50 60 60 70 70 80 80 90 90 100 100

150 150 4587 4587 4710 4710 4831 4831 5071 5071 5311 5311 5483 5483 5655 5655 5792 5792 5927 5927 6162 6162 6397 6397

>150

> 150  ::;1000 1000 4667 4667 4801 4801 4935 4935 5180 5180 5425 5425 5594 5594 5762 5762 5905 5905 6048 6285 6285 6523 6523

> 1000

> 1000  ::;2000 2000 4717 4717 4867 5017 5017 5267 5267 5517 5517 5680 5680 5844 5844 5995 5995 6145 6384 6623 6623

>2000

>2000  ::;3000 3000 4755 4909 5063 5063 5320 5320 5578 5578 5740 5740 5902 6052 6201 6201 6442 6442 6683 6683

> 3000

> 3000  ::;4000 4000 4818 4975 5131 5131 5396 5396 5660 5660 5814 5814 5969 5969 6113 6257 6483 6708

>4000

> 4000  ::;5000 5000 4767 4920 5072 5346 5619 5778 5938 6073 6208 6439 6670

> 5000

> 5000  ::;6000 6000 4717 4865 5013 5296 5579 5743 5906 6033 6159 6395 6631

> 6000

>  ::;7000 7000 4689 4827 4965 5254 5542 5542 5714 5885 6001 6118 6355 6593

> 7000

> 7000  ::;8000 8000 4660 4788 4916 5211 5506 5685 5864 5970 6076 6316 6555

> 8000  ::;9000 9000 4646 4765 4884 5182 5480 5669 5857 5955 6052 6292 6531

>> 9000 9000  ::;10000 10000 4632 4742 4852 5154 5455 5652 5850 5939 6028 6268 6507

>10000

>10000  ::;11000 11000 4622 4725 4828 5129 5431 5641 5850 5933 6016 6253 6490

>11000

>11000  ::;12000 12000 4612 4707 4803 5105 5408 5629 5850 5927 6004 6239 6473

>12000

>12000  ::;13000 13000 4617 4706 4795 5096 5398 5631 5865 5937 6010 6242 6475

>13000

>13000  ::;14000 14000 4621 4704 4787 5087 5387 5633 5879 5947 6015 6245 6476

>14000

>14000  ::;15000 15000 4631 4709 4787 5086 5385 5642 5900 5964 6028 6256 6485

>15000  ::;16000 16000 4641 4714 4787 5085 5382 5652 5921 5981 6041 6267 6493 6493

>16000

>16000  ::;17000 17000 4662 4731 4800 5096 5391 5669 5669 5947 6004 6062 6062 6286 6510

>17000  ::;18000 18000 4682 4748 4813 5107 5400 5687 5973 6028 6083 6304 6526 6526

>18000 :5:19000 19000 4709 4771 4833 5125 5418 5710 6002 6056 6109 6328 6547

>19000 :5:20000 20000 4735 4794 4852 5144 5144 5435 5734 6032 6032 6083 6135 6351 6568 6568

>20000

>20000 :5:20885 20885 4760 4818 4818 4876 5165 5165 5454 5454 5759 5759 6063 6063 6112 6112 6161 6161 6377 6377 6592 6592 Notes:

Notes:

1.

1. Rod Rod worth worth data data assumes assumes the the starting starting point point isis rods rods at at the If aa bank Limit. If Insertion Limit.

Rod Insertion the Rod below the is below bank is RIL, reduce the RIL, the reduce the table value table value byby 75 75 pcm pcm for for each each step step below below the the RIL.

RIL.

2.

2. The The rod rod worth worth data data represents represents negative negative reactivity.

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

STP.

3.

3. ARI-l ARI-1 is defined as is defined as All All Rods Rods InIn --less

-- less the the most reactive rod.

most reactive rod. The requires that calculation requires SDM calculation The SDM rod be one rod that one assumed be assumed stuck. Therefore, stuck. Therefore, use use the the data data directly directly from from the the table table above above when when there there are are not not any any known known stuck stuck rods.

rods.

of 22 Page 11 of Page

Westinghouse Proprietary Class 2 PCB-I-VOLl-CRV77 PCB-1-VOL1-CRV77 UNIT 11 CYCLE 23 CURVE 77 Control Rod Worth for SDM Calculations REV.~

REv.g

/#

APPROVED:

APPROVED: y ~ k. f-o/

/i lor bygrrtf~ (1'I-:,ltr (rr ENGINEERING SUPPORT MANAGER DATE Worth of Most Reactive Rod (pcm) for Shutdown Margin Calculations Bumup Burnup Range Power Level (MWDIMTU)

(MWD/MTU) 0% to 100%

150 150 658

> 150  ::;1000 1000 676

>1000

> 1000  ::;2000 2000 732

>2000

> 2000  ::;3000 3000 781

>3000

> 3000  ::;4000 4000 889

>4000

> 4000  ::;5000 5000 1024

> 5000  ::;6000 6000 1160

> 6000  ::;7000 7000 1232

> 7000

>  ::;8000 8000 1304

> 8000

>  ::;9000 9000 1355

> 9000

>  ::;10000 10000 1406

>10000  ::;11000 11000 1450

>11000  ::;12000 12000 1494

>12000 $;13000 13000 1528

>13000  ::;14000 14000 1561

>14000  ::;15000 15000 1592

>15000 $;16000 16000 1623

>16000  ::;17000 17000 1653

>17000  ::;18000 18000 1684

>18000  ::;19000 19000 1713

>19000  ::;20000 20000 1741

>20000  ::;20885 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 arid 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. less the most reactive rod.

ARI-1 is defined as All Rods In --less

4. ARt-i value on Page 11 of this curve should be reduced by the following calculation:

For multiple stuck rods, the ARl-l 1.751 +

[KUR x WSR x 1.75} + [WSR x 0.75]

0.751 where KUR = = Number of known untrippable rods (does not include rod assumed stuck in ARl-l ARI-1 table) and WSR = = Worst stuck rod (i.e. most reactive rod)

Page 2 of2 of 2

Westinghouse Proprietary Class 2 PCB-l-VOLI-CRV78 PCB-1-VOL1-CRV78 UNIT 11 CYCLE 23 CURVE 78 Total Power Defect for SDM 5DM Calculations REV.~

REV.

APPROVED: ~'1;1 (<L<f j"r fjrya", 41',-",,, ~

ENGINEERiNG SUPPORT MANAGER ENGINEERING 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

~150 0 361 537 717 898 958 1019 1119 1219 1326 1432

> 150

>150 1000

~1000 0 351 522 701 879 943 1006 1106 1206 1307 1409

>1000 2000

~2000 0 330 495 667 839 903 967 1068 1169 1265 1361

>2000

> 2000 3000

~3000 0 317 476 647 818 879 941 1041 1142 1237 1332

> 3000

>3000 4000

~4000 0 326 489 664 839 901 964 1062 1161 1261 1360

> 4000

>4000 ~ 5000 0 344 514 697 879 942 1004 1103 1202 1306 1410

> 5000 6000

~6000 0 362 539 729 919 982 1045 1144 1242 1351 1459

> 6000 7000

~7000 0 388 576 774 972 1037 1103 1202 1301 1416 1531

>7000 8000

~8000 0 414 613 818 1024 1092 1160 1260 1360 1481 1603

> 8000 9000

~9000 0 440 651 863 1074 1147 1220 1326 1431 1558 1684

>9000 10000

~10000 0 466 690 907 1124 1202 1280 1391 1503 1634 1765

>10000 11000

~11000 0 492 728 950 1173 1258 1344 1461 1579 1717 1854

>11000 12000

~12000 0 518 766 994 1222 1315 1408 1531 1655 1800 1944

>12000 13000

~13000 0 543 804 1035 1267 1369 1471 1603 1734 1884 2034

>13000 14000

~14000 0 567 841 1077 1313 1424 1535 1674 1813 1968 2123

>14000 15000

~15000 0 589 875 1115 1356 1477 1597 1744 1890 2054 2217

>15000 16000

~16000 0 611 908 1153 1399 1529 1660 1813 1967 2139 2310

>16000 17000

~17000 0 633 940 1189 1438 1578 1718 1882 2046 2223 2400

>17000 ~18000 18000 0 654 971 1225 1478 1627 1777 1951 2125 2307 2489

>18000 19000

~19000 0 673 1001 1259 1516 1677 1837 2020 2203 2392 2582

>19000 20000

~20000 0 692 1031 1293 1554 1726 1897 2089 2280 2477 2674

>20000 ~20885 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 1I Cycle 23 Revision 0 Page 10 of 13 Figure 11 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 II n. I I I..- (.552,225)

IJ 200 IJ (1,187)_

175 ~ "'"

, ~

Banke "2 C

~ 150 ~ ~

IV "C

.s::::

§ li

0. 125 ~

~

~

.sU)

~ ~

c::

C (0, 114) ~

00

• iii 0 100 00 1..-

c...

0

~ Bank D c::

C IV

/Xl "C 75 00 ~

0:::

50

~

25

, ~

(.070,0)

I I I I I o0 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 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.

FNPHLT-33 FNP HLT-33ADMIN ADMIN A.2.IA A.2.1.A HANDOUT HANDOUT Pg Pg I1 of of II CONDITIONS CONDITIONS When II tell When tell you you toto begin, begin, you you are are to to Determine Determine if if Shutdown Shutdown Margin Margin isis adequate adequate using using STP-29.5, STP-29.5, SHUTDOWN MARGIN SHUTDOWN MARGIN CALCULATION CALCULATION IN IN MODES MODES 11 AND AND 22 (TAVG (TAVG 2:: 547°F),

547°F), for for Unit Unit I.1. The The conditions under conditions under which which this this task task is is to to be be perfonned performed are:

are:

a.

a. Unit II is Unit stable at is stable 90% with at 90% with the the ramp ramp on hold on hold

b. Bank 0D indicates 192 192 by Group Demand.

c. Seven of the Bank 0D rods (H2, B8, H14, F6, FlO, KlO, Kb, K6) are at 192 192 steps by DRPI.

d. Rod P8, in in the 0D bank, has been detennined determined to be Stuck.

e.

e. Rod P8 is Rod 162 steps is at 162 steps by DRP!.

DRPI.

f. All other rods rods are atat 229 steps.

g. burnup is 9,800 MWD/MTU bumup.

Core bumup

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

547°F), initial conditions are satisfied.

i. The Shift Supervisor has directed you to complete FNP-1-STP-29.5

1. FNP- I -STP-29.5 starting at step 5.1.

HLT-33 FNP HL T-33 ADMIN Page 11 of5 of 5 A.3.1.A Radiation Control ADMIN G2.3.9 - RO & SRO SRO CRO-A.3.1.A TITLE: Calculate the Maximum Permissible Stay Time within Emergency Dose Limits.

PROGRAM APPLICABLE: SOT SOCT____ OLT~

SOCT OLT X LOCT __

LOCT____

ACCEPTABLE EV EVALUATION ALUA TION METHOD: ~ X PERFORM SIMULA SIMULATE TE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM ----.lL X CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: NIA N/A ALTERNATE PATH TIME CRITICAL PRA __

PRA____

JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

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 1I through 7 may be evaluated by reviewing the responses on the Handout.

TASK STANDARD: Required for successful completion of this jPM: JPM:

• Calculate dose expected for Tasks 11 through 3
• Determine if a Repair team would exceed equipment protection emergency dose limits of EIP- 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 0 Unsatisfactory 0D Evaluator Comments (attach additional sheets if necessary)

EXAMINER: _ _ _ _ _ _ _ _ ___

Developer Howard Fitzwater 1 1/06/09 11/06/09 NRC Approval SEE NUREG 1021 1021 FORM ES-301-3

FNP HL FNP HLT-33 ADMIN T-33 ADMIN A.3.1 .A A.3.1.A Page Page 22 of5 of 5 CONDITIONS CONDITIONS When II tell When tell you you toto begin, begin, you are to you are to determine determine if if exposure exposure isis within within emergency emergency dosedose limits limits of of EIP-EIP 14.0, Personnel Movement, 14.0, Personnel Movement, Relocation, Relocation, Re-Entry Re-Entry and and Site Site Evacuation.

Evacuation. The The conditions conditions under under which which this task this task is is to to be performed are:

be performed are:

a. A General Emergency has has been declared on on Unit 1.1.

b. lA

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

c. The

c. The TSC TSC has requested that that 1lB B RHR pump motor bearing bearing oil oil levels levels be checked checked and and filled filled as required after restoring lA IA RHR and suggests using the same Repair team. The time required to perform this task is unknown, but is estimated to range between 11 to 20 minutes.

d. 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 1I 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. EIP- 14.0.

• If any member of the team will NOT exceed 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 limits prior to performing task 4, THEN identify the last tasks (if any) that the team can complete without either member exceeding dose limits.

Time allowed/

allowed! Dose Task Location/Task description req'd reqd Rate Dose

1. ft (minutes) (R/hr)

(RIhr) 83' 11A 83 A RHR Pump and HX rooms! rooms/ Vent rig installation and 1

venting 30 55.31 31 100 piping penetration room!

100' room/ Vent rig installation and 2 15 19.75 19 75 venting 121 piping penetration room! Vent rig installation and 121' 3 20 55.65 65 venting Inspect 1IB B RHR pump motor bearing oil levels and fill as 4

required 77 Year-to-date DOSE Records (REM TEDE)

TED TED 1.26 1.26 JOEL 0.4 Can this team perform all of the tasks? (Circle one) YES !I NO IF yes, IF yes, then state the maximum then state maximum permitted stay stay time time for task #4.

IF no, then IF then state the highest sequential state the sequential task task ## that can can be be performed, performed, if if any.

any.

INITIATING INITIATING CUE: CUE: You may begin.

"You may begin."

FNP HLT-33 FNP HLT-33 ADMINADMIN A.3.1.A A.3.1.A Page Page 33 of5 of 5 EVALUATION CHECKLIST EVALUATION CHECKLIST RESULTS:

RESULTS:

ELEMENTS:

ELEMENTS: STANDARDS:

STANDARDS: (CIRCLE)

(CIRCLE)

START TIME START TIME

1. Determine

1. Determine the dose dose received for for tasks 11 through 3.

3. 1)

1) Calculates Calculates (in (in REM)

REM)

• Task#1

a. Task #1 a. 2.66 {Range

{Range 2.6 to 2.7} S I/ U (30min)x 5.31R/hr (30min)X5.31Rlhrx( ( lhr

= 2.66REM lhr. )=2.66REM 60 mm }

60mm Task #2

b. Task#2

• 1h

b. 4.938 {4.9{4.9 to 5.0} S II U U (I5min)x19.75RIhrx (15min)XI9.75Rlhrx( =4.938REM lhr. )=4.938REM 60mmn}

60mm

• c. Task #3 lhr c. 1.88 {1.8 to 1.9}

{l.8to SS/UI U (20min)x 5.65R / hr x (20min)X5.65Rlhrx( 1 Ihr. )=1.88REM

=1 .88REM 60min,)

60mm NOTE:

• A Cue may be required to obtain responses for each element if the candidate does not clearly document results. Provide the Cue as stated on the Handout.

clearl

• 2. Evaluates Team exposure within emergency 2) Circles YES on handout -OR- OR S I/ UU of EIP-14.0 for completion of tasks 1I limits ofEIP-14.0 states that team can perform through 3. tasks 1I through 3.

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

b. Summation of Task 11 through 33 (2.66 +

11 OREM -(2.66 1 .88)REM ~ 0

+ 4.94 + 1.88)REM b. 0.52 R remains available 0.52REM0 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 SS /I UU 4 hr V6OminN time is 4.5 mins (0.52Rem{ hr )(60min)

(0.52Rem I = 4.493 min 1=4.493mm

\7 7REM,A REM hr ,)

. . min to 66 mm)

{Range: 33 mm min)

{RANGE

{RANGE:: 3mmnto6mmn}

3 min_to _ 6min}

STOP TIME STOP Terminate when all elements of of the task have been been completed.

CRITICAL ELEMENTS:

CRITICAL ELEMENTS: Critical Critical Elements Elements areare denoted denoted with with an asterisk (*)

an asterisk before the

(*) before the element element number.

number.

FNP HLT-33 ADMIN A.3. 1 .A A.3.I.A Page 4 of5 of 5 GENERAL

REFERENCES:

I. FNP-O-EIP-I4.0,

1. FNP-0-EIP-14.0, ver ver22 22 FNP-0-M-1.0, ver 18.0

2. FNP-O-M-l.O, 18.0 G2.3.4

3. KA: 02.3.4 RO 3.2 SRO 3.7 GENERAL TOOLS AND AN]) EQUIPMENT:

Provide/Acquire:

1. Computer with access to Exam Reference Disk, or EIP 14.0, ver 22.0 and M-I.O, M- 1 .0, version 18.0.

1 8.0.

2. Calculator

3. pens/pencils

4. Scrap paper Critical ELEMENT justification:

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

Teds year to date dose is used, the emergency dose limit will be exceeded and the expected response IF Ted's NO and highest task that can be completed is Task #3.

for element 2 is "NO" IF Joel's 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 of22 REM used then NONE of the tasks can be performed, or Legal limit of 55 REM then Task #2 will be the highest.

FNP HL FNP HLT-33 ADMIN T -33 ADMIN A.3.1.A A.3.1.A HANDOUT HANDOUT Page 11 of Page of 1I CONDITIONS CONDITIONS When II tell When tell you you to to begin, begin, youyou are are to determine if to determine if exposure exposure isis within within emergency emergency dose dose limits limits of of EIP-EIP 14.0, Personnel 14.0, Personnel Movement, Movement, Relocation, Relocation, Re-Entry Re-Entry and and Site Site Evacuation.

Evacuation. The The conditions conditions underunder which which this task this task is is to to be performed are:

be performed are:

a.a. A General Emergency A General Emergency has has been been declared declared on on Unit Unit 1.1.

b. 1IA

b. RHR pump A RHR pump is air bound is air bound and and must must bebe vented vented perper AOP-12, AOP-12, Attachment Attachment 1, I, RHR RHR Pump Pump Venting.

Venting.

c. The

c. The TSCTSC hashas requested requested that that 1I B RHR pump B RHR pump motor motor bearing bearing oiloil levels levels bebe checked checked and and filled filled as as required after required after restoring restoring 1IA RHR and A RHR and suggests suggests using the the same same Repair Repair team.

team. The The time required required toto perform this task is unknown, perform this task is unknown, but is estimated to range but is estimated range between 1I to 20 minutes. minutes.

d. Ted

d. Ted andand Joel Joel have have been been selected selected toto perform perform thethe task, task, their their exposure exposure information information is is stated stated below.

below.

e. The The Tasks are provided in the table below, and estimated times and doses have have been provided.

provided.

Each task must f.f. Each must be completed completed by by both operators, and must must be performed in in the the order listed.

listed.

operators

g. Both operators are are expected expected to receive equalequal dose dose for for each each job.

h. The Emergency Director (ED) directs you to perform the following with the information provided:

provided:

o Calculate the expected dose for tasks 11 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. El P-I 4.0.

• If any member of the team will NOT exceed 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 limits prior to performing task 4, THEN identify the last tasks (if any) that the team can complete without either member exceeding dose limits.

Time allowed/

allowed! Dose Task Location/Task description Location/Task req'd reqd Rate Dose

1. (minutes) (Rlhr)

(R!hr) 83' 1IA 83 A RHR Pump and HX rooms! rooms/ Vent rig installation and 11 venting 30 55.31 31 100 piping penetration room!

100' room/ Vent rig installation and 22 15 19.75 19 75 venting 121 121 ' piping penetration room! room/ Vent rig installation and 3 venting 20 55.65 65 Inspect Inspect I1B B RHR pump motor bearing oil oil levels levels and and fill as 4 required 77 required Year-to-date Year-to-date DOSE DOSE Records (REM (REM TEDE)

TEDE)

TED TED 1.26 1.26 JOEL JOEL 0.4 0.4 Can Can this team perform this team perform all all of of the the tasks?

tasks? (Circle (Circle one) one) YES YES  !/ NO NO IF IF yes, yes, then then state the maximum state the maximum permitted permitted stay stay time time for for task task #4.

1. 4.

IF IF no, no, then state the then state the highest highest sequential task ## that sequential task that can can be be performed, performed, if if any.

any.

FNP HLT-33 ADMIN Page 11 of6 of 6 G2.4. 14 - RO & SRO A.4.1.A Emergency Plan G2.4.14 CRO-A.4. 1 .A CRO-A.4.1.A TITLE: Monitor the Critical Safety Function Status Trees.

PROGRAM APPLICABLE: SOT SOCT OLT X LOCT LOCT______

ACCEPTABLE EVALUATION METHOD: ~ X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: ~ X SIMULATOR PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: IC-216 ALTERNATE PATH TIME CRITICAL PRA __

PRA____

JPM DIRECTIONS:

1. This task will be conducted on the Simulator.

2. The simulator will remain frozen for the duration to the task, if the candidate attempts to operate any component, no plant response will occur.

3. The plant computer screens will be turned off.

4. ALL will perform elements 11 through 7.

5. ONLY SRO will perform elements 8-10.

TASK STANDARD: Required for successful completion of this JPM:

• Identify Identi1v all applicable Critical Safety functions which are challenged.
• Identify the highest level challenge to the CSFSTs and the required procedure entry, if any.
• SRO ONLY: Perform a proper assessment and procedure transition for the given conditions.

Examinee:

Overall JPM Performance: Satisfactory 01 Unsatisfactory 0D Evaluator Comments (attach additional sheets if necessary)

EXAMINER: _ _ _ _ _ _ _ _ ___

Developer Howard Fitzwater 1 1/09/09 11109/09 LNRC Approval SEE NUREG 1021 FORM ES-301-3

FNP HLT-33 FNP HLT-33 ADMIN ADMIN A.4.1.A AA.l.A Page Page 22 of6 of 6 CONDITIONS CONDITIONS When II tell When tell you to begin, you to begin, you are to you are to monitor monitor thethe Critical Critical Safety Safety Function Function Status Status Trees Trees (CSFST).

(CSFST).

The conditions under which The conditions which this this task task is is to to be be performed are:

are:

a. A Large Break

a. Break LOCA and loss of Off-site Off-site power has has occurred on on Unit 1I from from 100%

100% 10 10 minutes ago.

b. The

b. The team has transitioned team has transitioned toto EEP-1.0, Primary or EEP-l .0, Primary or Secondary Secondary Loss Loss of of Coolant.

Coolant.

c. The Integrated

c. The Integrated Plant Computer Computer has failed.

failed.

d. The STA is en route to the Control Room.

e. You have been directed to manually monitor Critical Safety Functions using CSp -0.0, Critical CSF-0.0, Safety Function Status Trees and:

identify all applicable Critical Safety functions which are challenged, if any.

1. Identify 1.

2. If applicable, identify the highest level challenge to the CSFSTs and the required procedure entry for that condition.

INITIATING CUE: "You You may begin."

begin.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME I.

1. Evaluates CSFST at CSF-O.l CSF-0.i Subcriticality. 1) Determines Subcriticality SAT / S / U GREEN.

a. Power Rng < 5% a. YES (N42 is failed high)

b. mt RNG SUR zero or neg Both Int b. YES

c. Both SR detectors ARE energized c. NO

d. IR Range <-0.2

< -0.2 DPM d. YES

2. Evaluates CSFST at CSF-0.2 CSF-O.2 Core Cooling. 2) Determines Core Cooling OFF- S S / U NORMAL / YELLOW (C.3).

a. CET<1200°F CET <1200 of a. YES

b. Subcooling> 16°F 16°F {45°} b. NO

c. CET <700 °F of c. YES 3.

3. Evaluates CSFSTCSFST at CSF-0.3 CSF-0.3 Heat Sink.Sink. 3) Determines Heat Sink is OFF-

3) SS / UU NORMAL / YELLOW YELLOW (H.5).

a. NR levels> 31 {48%} {48% } a. NO b.

b. Total AFW flow >395 gpm.

Total gpm. b.

b. YES YES c.

c. Press in Press SG <1129 in all SG <1129 psig psig c.

c. YES YES d.

d. NR lvl NR lvl <82%

<82% d.

d. YES YES e.

e. Press <1075

<1075 psigpsig e.

e. YES YES

f. NR lvl >31 % {48%}

NRlvl>31%{48%} f. NO

FNP HLT-33 FNP HLT-33 ADMIN ADMIN A.4.1 .A AA.l.A Page Page 33 of6of 6 EVALUATION CHECKLIST EVALUATION CHECKLIST RESULTS:

RESULTS:

ELEMENTS:

ELEMENTS: STANDARDS:

STANDARDS: (CIRCLE)

(CIRCLE)

NOTE:

NOTE: Candidate may Candidate may inform inform the the SS SS of ofthe the FRP-P.lI FRP-P.1/ ORANGE ORANGE path path condition condition upon upon discovery discovery butbut should continue should continue to to evaluate evaluate the remaining CSFSTs.

the remaining CSFSTs. IFIF CUE CUE required, required, then then provide:

provide: "SS SS Acknowledges.

Acknowledges."

• 4.

4. Evaluates CSFST Evaluates CSFST atat CSF-OA CSF-0.4 INTEGRITY.

INTEGRITY. 4) Determines Determines Integrity is is SS // UU SEVEREL SEVERELY Y Challanged Challanged //

ORANGE.

ORANGE. (P.I) (P.1)

Temp decr <100 OF

a. Temp °F last 60 min mm a.

a. NO

b. All Press and CL temps to right of LIMIT A b. YES (LOSP will result in instrument spike < < 250F-25 OF-indication only-should onlyshould be determined as not valid).

c. Al I1 CL temps> 250°F c. NO NOTE: ** The candidate may inform the SS of the FRP- Z.1I0RANGE Z. 1/ORANGE path condition upon discovery but should continue to evaluate the remaining CSFSTs. IF CUE required, then provide: "SS SS Acknowledges.

Acknowledges."

5. Evaluates CSFST at CSF-0.5 Containment Containment.. 5) Determines containment is in S / U U SEVERELY SEVEREL Y Challenged/

Challenged!

ORANGE (Z.1) (Z.l)

a. CTMT press <54 psig a. YES

b. CTMT press <27 psig b. NO (35 psig)

c. AT least ONE CTMT Spray pump running c. NO; recognizes 1 B CS IB with flow flow>>1000 1000 gpm. pump has no flow path (MOV -8820B aligned (MOV-8820B closed) and IA lA CS pump pump is not running.

6.

6. Evaluates Evaluates CSFST CSFST atat CSF-0.6 CSF-0.6 INVENTOR INVENTORY. Y. 6) Determines

6) Determines containment containment isis in in SS // UU OFF-NORMAL OFF-NORM / YELLOW AL / YELLOW (1.2).

(1.2).

a. PRZR

a. PRZR level level <92%

< 92% a. YES

a. YES

b. PRZR

b. PRZR level>

level> 15%

15% b. NO b.NO

HLT-33 ADMIN FNP HLT-33 A.4.1 .A A.4.1.A of 6 Page 4 of6 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

• 7. Reports to the Shift Supervisor identified 7) SS informed of FRP Z.I P.1 Z.1 and P.I S / U FRP-P.1 is highest priority:

conditions and FRP-P.I ORANGE paths exist and FRP- FRP P.1 entry required.

P.I FRP-P. 1, ORANGE due to Cooldown

a. FRP-P.l,

>100°F

> 100°F in 60 minutes and <

< 250°F.

FRP-Z.1 ORANGE due to failed IA CTMT

b. FRP-Z.l Spray pump and 1I B CTMT Spray pump discharge valve.

RO ONLY: Terminate when Elements 1-7 have been completed.

IF element 7 correctly assessed then:

SRO CUE: "SS SS acknowledges and directs you to perform FRP-P.l."

FRP-P. I .

8. (FRP-P.l Step 1)I) Checks RCS pressure Greater 8) RCS pressure checked on S / U than 435 psig: P1-402B and 403B (50 PI-402B psig) and determined less than.

9. (FRP-P.l step 1I RNO) Checks LHSI flow 9) Checks flow on FI-605A and S / UU greater than 1500 gpm. F1-605B. (3250 gpm)

FI-605B.

• • 10. Transitions to procedure step in effect. 10) Properly assesses Procedure S S / UU FRP-Z.I.

step in effect is FRP-Z.l.

Transitions to FRP-Z.l or states the FRP-Z.1 FRP-Z.l is required to be entered.

STOP TIME II SRO ONLY: Terminate when all Critical Elements have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) (*) before the element number.

FNP HL HLT-33 T-33 ADMIN A.4.l.A A.4.1.A of 6 Page 5 of6 GENERAL

REFERENCES:

1. CSF

1. CSF-0.0, 17.0

-0.0, ver 17.0

2. FNP-1-FRP-P.1, ver 19

3. KA: G2.4.14 RO 3.8 SRO 4.5 GENERAL TOOLS AND EQUIPMENT:

NONE Critical ELEMENT justification:

STEP Evaluation I

1 criticalprocedure protocol, NOT critical-procedure protocol , condition not challenged (GREEN) 2 criticalprocedure protocol, conditions Off-Normal (Yellow)

NOT critical-procedure 3 criticalprocedure protocol, condition Off-Normal (¥ellow)

NOT critical-procedure (Yellow) 4 CRITICAL - Task Objective, condition CHALLENGED (ORANGE) 5 CRITICAL - Task Objective, condition CHALLENGED (ORANGE) 6 criticalprocedure protocol, condition Off-Normal (Yellow)

NOT critical-procedure 7 CRITICAL - Task Objective, reports both challenged conditions to SS and identifies highest priority procedure. (END RO ONLY) 8 criticalprocedure protocol NOT critical-procedure 9 criticalprocedure protocol NOT critical-procedure 10 Task Objective; properly assess next procedure transition for CRITICAL -Task conditions. (END SRO ONLY)

COMMENTS:

If the candidate attempts to operate the CTMT Spray pump or discharge valve, and notes that the The response is as you see it."

simulator is frozen, a Cue may be required: "The it.

FNP HLT-33 FNP l-ILT-33 ADMIN ADMIN A.4.1.A A.4.I.A HANDOUT HANDOUT Page 11 of Page of 1I CONDITIONS CONDITIONS When II tell When tell you you toto begin, you are begin, you are to monitor the to monitor Critical Safety the Critical Safety Function Function Status Trees (CSFST).

Status Trees (CSFST).

The conditions The conditions under which this under which this task task isis to to be be performed performed are:

are:

a.a. A A Large Break LOCA Large Break LOCA and and loss loss of of Off-site Off-site power power has occurred on has occurred on Unit Unit 11 from from 100%

100% 1010 minutes minutes ago.

ago.

b. The

b. The teamteam has transitioned to has transitioned EEP-I.0, Primary to EEP-I.O, Primary oror Secondary Secondary Loss Loss of of Coolant.

Coolant.

c. The

c. The Integrated Integrated Plant Computer has Plant Computer has failed.

failed.

d. The

d. The ST STAA isis en en route route to to the Control Room.

the Control Room.

e. You have been directed to

e. You have been directed to manually monitormanually monitor Critical Critical Safety Safety Functions Functions using using CSF -0.0, Critical CSF-0.0, Critical Safety Function Status Safety Function Status Trees Trees and:

and:

I.I. Identify Identify allall applicable applicable Critical Critical Safety functions which Safety functions which are challenged, if are challenged, if any.

any.

2. If applicable, identify the the highest level challenge to the CSFSTs and the required procedure entry for that that condition.

condition.