ML080280348

Nov/Dec 2007 Exam 05000348-07-301 & 05000364/2007301- Post-Exam Comments Ltrs Dtd 12-7-2007 & 1-4-2008

ML080280348
Person / Time
Site:	Farley
Issue date:	01/28/2008
From:	Southern Nuclear Operating Co
To:	NRC/RGN-II
References
50-348/07-301, 50-364/07-301
Download: ML080280348 (94)

See also: IR 05000348/2007301

Text

POST-EXAM COMMENTS (Green Paper)Licensee Submitted Post-Exam Comments

I

TES,)L 7Je j)7);>fiJi/os hit-

[]None FARLEY NOVEMBER-DECEMBER 2007 EXAM NOS.

POST-EXAM COMMENTS

Southern Nuclear Operating Company, Inc.Post Office Drawer 470 Ashford, Alabama 36312 Tel 334.8995156

Fax 334.814.4661

FNP-2007-0148-TRN

5 12/07/2007

Mr.Frank Ehrhardt United States Nuclear Regulatory

Commission

Sam Nunn Atlanta Federal Center 61 Forsyth Street SW, Suite 23T85 Atlanta, Georgia 30303-8931

Dear Mr.Ehrhardt, Energy to Serve lOur World sM Concerning

the Farley HLT-31 NRC Exam, administered

on the weeks of November 5,2007 and November 13, 2007 at Farley Nuclear Plant, attached is a three page document entitled"Post Exam Comments On: A.1.1 Conduct of operations

ADMIN G2.1.10-SRO".Changes Requested based on supporting

document pages 1-3 of 3 attached:*Make element 3 non-critical

for consistency

with all the other conditions

in this task that do NOT preclude Mode 4 entry based on the literal interpretation

of our licensing documents Technical Specifications

and Bases.This leaves two other critical tasks which must be properly evaluated to determine Mode 4 entry IS prohibited

for reasons other than the EDG inoperability.

• Element 3 stated that the 1B DG was required to be immediately

declared inoperable

due to low fuel oil supply.This is incorrect due to the 1B DG not being required in mode 5, and the DG is required to be declared inoperable

only in the mode in which it is required.Element 3 should say that"an Admin LeO must be written for the IB DG" (This is required by Farley policy, but not by Technical Specifications, and this is not a critical task due to it not being a mandatory LCO).This material discusses a part of this exam that has already been administered.

If you have any questions, please contact Charles V.(Vince)Richter at (334)814-4758.onna M.Christiansen

OPS Training Supervisor

CVR/DMC:las

cc: FIle o

Attached to letter FNP-2007-0l48-TRN

Concerning:

Farley NRC Exam 3012007, Week of NOV 5, 2007 Post Exam Comments On: A.l.l Conduct of operations

ADMIN G2.l.l0-SRO POST EXAM COMMENTS ON: A.l.l Conduct of operations

ADMIN G2.l.l0-SRO CHANGE REQUESTED:

• Make element 3 non-critical

for consistency

with all the other conditions

in this task that do NOT preclude Mode 4 entry based on the literal interpretation

of our licensing documents Technical Specifications

and Bases.This leaves two other critical tasks which must be properly evaluated to determine Mode 4 entry IS prohibited

for reasons other than the EDG inoperability.

• Element 3 stated that the lB DG was required to be immediately

declared inoperable

due to low fuel oil supply.This is incorrect due to the lB DG not being required in mode 5, and the DG is required to be declared inoperable

only in the mode in which it is required.Element 3 should say that"an Admin LCO must be written for the 1 B DG" (This is required by Farley policy, but not by Technical Specifications, and this is not a critical task due to it not being a mandatory LCO).SUMMARY: This task presented initial conditions

for evaluation

to determine if Mode 4 entry from Mode 5 was allowed.Several items were evaluated, and three conditions

were intended to preclude Mode 4 entry.Identifying

these three items correctly were critical tasks.The IPM also required evaluating

several other items that would not prevent a Mode 4 entry, and identifying

these correctly were not critical tasks.Element 3 required declaring the lB DG inoperable

due to low fuel oil supply, which precluded a mode change from Mode 5 to Mode 4.Two trains of DGs are required in Mode 4 and the lB DG is considered

to be one entire train or set.(1-2A and lC DG are considered

to be the A Train set This is consistent

with Plant Policy and management

expectations (which is not written down), but not with the Technical Specifications

and bases as written in Action B (note LCO 3.0.4c).In Element 3, Plant Policy and management

expectations

require both trains of DGs to enter Mode 4, but the Technical Specification

is written to allow Mode 4 entry as long only one of the 3 DGs is inoperable (including

the lB EDG, even though it is one train by itself).The plant policy has been that the clause in Tech Specs allowing mode change with only one of the three DGs inoperable

applied only to the two"A" Train DGs which are shared between units.For the A Train DGs, either DG being inoperable

does not completely

eliminate an entire train to either unit.The B Train DGs are unit specific and treated differently

as standalone

DG trains.This policy and expectation

is not documented

in approved plant procedures

which precluded providing the applicants

with this information

for their evaluation.

Previous training and knowledge of on-shift plant-practice

is required to determine this interpretation.

Subsequent

to this operating exam, a post exam condition report will be written to include documenting

this policy.The students were provided the Technical Specifications

and Bases for TS 3.8.1: AC SourcesOperating,&T.S.3.8.3: Diesel Enel Oil, IJJhe OJ], and Starting Air All Technical Specifications

and bases were available on request.Based on a literal interpretation

of these documents, the applicants

would determine Mode 4 entry was NOT precluded by the lB DG being inoperable, as long as lC&l-2A (both A Train DGs)were operable as was the case in this task.Page 1 of 3

Attached to letter FNP-2007-0148-TRN

Concerning:

Farley NRC Exam 3012007, Week of NOV 5, 2007 Post Exam Comments On: A.1.1 Conduct of operations

ADMIN G2.1.10-SRO The Technical Specification

guidance and Plant procedure are explained below:*The 1B DG is required to be declared inoperable

in Mode 4, due to low fuel oil supply, which precludes a mode change from Mode 5 to Mode 4.Two trains of DGs are required in Mode 4 and the 1B DG is one entire train.One of two required trains being inoperable

would normally preclude a mode change, and plant management

expectations

and past practice requires not changing modes without both trains of DGs, even though the Technical Specifications

allow it per the following:

o There is a stated allowance for the mode change in a note in the DG Technical Specification

3.8.1, REQUIRED ACTION B: "LCO 3.0.4c is applicable

when only one ofthethree DGs is inoperable".

LCO 3.0.4c states: "When an LCO is not met, entry into a MODE or other specified condition in the Applicability

shall only be made: (c.)When an allowance is stated in the individual

value, parameter, or other Specification

[in this case, the allowance is made in the Specification

in the note of3.8.1]" o The 1B DG is the only DG inoperable

as presented in the conditions

given, so per the note in TS 3.8.1, the mode change may occur.o STP-35.1, Mode change procedure, Step 4.2, states: Units 1/2 Technical Specifications

Amendments

170/163, INCREASING

FLEXIBILITY

IN MODE RESTRAINTS, issued 02-22-2006, revised LCO 3.0.4 to allow entry into a MODE while relying on the associated

ACTIONS, provided that either***(a)the ACTIONS to be entered permit continued operation in the MODE for an unlimited period of time, (b)a risk assessment

is performed which justifies the use of LCO 3.0.4 (unless there's an exception in the Specification), or (cl an NRC approved allowance is provided in the Specification

to be entered..o The note in TS 3.8.1 REQUIRED ACTION B allows mode change with only one of the 3 required DGs inoperable, and is an NRC approved allowance provided in the Specification

[3.8.1]to be entered.Page 2 of 3

Attached to letter FNP-2007-0148-TRN

Concerning:

Farley NRC Exam 3012007, Week of NOV 5, 2007 Post Exam Comments On: A.l.l Conduct of operations

ADMIN G2.1.10-SRO The following is from the ADMIN JPM A.I.I SRO ONLY"as administered":

TITLE: Determine if current conditions

allow Mode 4 entry TASK STANDARD: Determine while completing

a mode change checklist that mode 4 entry is prohibited

by two unsat STPs, STP-I0.4&STP-15, and an inoperable

IB DG (due to low Fuel Oil Storage tank content).CONDITIONS

When I tell you to begin, you are to determine if Mode 4 entry is allowed.IF mode 4 entry is prohibited, identify which conditions

preclude Mode 4 entry.a.Unit 1 is in Mode 5.b.You are the Shift Support Supervisor.

You are to complete filling out STP-35.1 and determine if Mode 4 entry is allowed.If any conditions

preclude Mode 4 entry, then identify all conditions

that preclude Mode 4 entry.c.Shift turnover and shift brief has just been completed.

1.STP-35.1, step 5.3, is in progress reviewing requirements

for Mode 4 entry.2.STP-l.0 has been performed 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago for mode 4.3.All STPs have been reviewed per FNP-l-STP-35.1E

with exceptions

noted on coversheet.

4.Taggout review is complete sat.5.All applicable

signatures

and initials have been completed in STP-35.1 except on the pages provided.6.Review for mode 4 LCOs has been completed except for DG which have parameters

listed: 1/2A lC IB Diesel Fuel Oil storage 25,500 gals 25,500 gals 20,350 gals tank contents Lube Oil inventory 248 gals 183 gals 255 gals Starting Air receiver 415 psig 240 psig 425 psig pressures Page 3 of 3

HLT-31 ADMIN exam A.1.1 SRO A.I.I Conduct of operations

ADMIN G2.1.10-SRO TITLE: Determine if current conditions

allow Mode 4 entry Page 1 of 5 TASK STANDARD: Determine while completing

a mode change checklist that mode 4 entry is prohibited

by two unsat STPs, STP-IO.4&STP-15, and an inoperable

IB DG (due to low Fuel Oil Storage tank content).PROGRAM APPLICABLE:

SOT SOCT OLTLOCT__ACCEPTABLE

EVALUATION

METHOD:PERFORM SIMULATE EVALUATION

LOCATION: X CLASS ROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA__DISCUSS Examinee: Overall JPM Performance:

Satisfactory

0 Unsatisfactory

0 Evaluator Comments (attach additional

sheets if necessary)

EXAMINER:_

HL T-31 ADMIN exam A.1.1 SRO Page 2 of 5 CONDITIONS

When I tell you to begin, you are to determine if Mode 4 entry is allowed.IF mode 4 entry is prohibited, identify which conditions

preclude Mode 4 entry.eVIew ormo e s as een compee excep or w IC ave parame ers I l/2A lC IB Diesel Fuel Oil 25,500 gals 25,500 gals 20,350 gals storage tank contents Lube Oil inventory 248 gals 183 gals 255 gals Starting Air receiver 415 psig 240 psig 425 psig pressures a.Unit 1 is in Mode 5.b.You are the Shift Support Supervisor.

You are to complete filling out STP-35.1 and determine if Mode 4 entry is allowed.If any conditions

preclude Mode 4 entry, then identify all conditions

that preclude Mode 4 entry.c.Shift turnover and shift brief has just been completed.

1.STP-35.1, step 5.3, is in progress reviewing requirements

for Mode 4 entry.2.STP-l.0 has been performed 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago for mode 4.3.All STPs have been reviewed per FNP-I-STP-35.1E

with exceptions

noted on coversheet.

4.Taggout review is complete sat.5.All applicable

signatures

and initials have been completed in STP-35.1 except on the pages provided.6R.£d4 LCO h bItdt£DG h*hht l*sted: EVALUATION

CHECKLIST ELEMENTS: STANDARDS:

RESULTS: (CIRCLE)START TIME*1.Determines

that STP-I0.4, EMERGENCY BORATION CHECK VALVES INSERVICE TEST, is UNSAT due to step 5.8 (IB BAT pump flow low).This precludes Mode 4 entry.Determines

that STP-I0.4, EMERGENCY BORATIONS/U CHECK VALVES INSERVICE TEST, is UNSAT due to step 5.8 flow lower than graph of 44 gpm (IB BAT pump flow low).This precludes Mode 4 entry.*2.Determines

that STP-15.0, CONTAINMENT

AIR LOCK DOOR SEAL OPERABILITY

TEST, is unsat due------t,-0--,S----:.2,...,.-.2Ol'IDT2347 sccm.This precludes Mode 4 entry.Determines

that STP-15.0, CONTAINMENT

AIR LOCKS/U DOOR SEAL OPERABILITY

TEST, is unsat due to 5.2.20 NOT2347 sccm.This precludes Mode 4 entry.

HLT-31 ADMIN exam A.1.1 SRO EVALUATION

CHECKLIST ELEMENTS:*3.Determines

that of the 9 given DG parameters, one makes the 1B DG inoperable

due to usable Fuel Level.This TS also requires immediately

declaring the IB DG inoperable.

This precludes Mode 4 entry due to two trains of DGs required in Mode 4.(SEE table on next page for KEY)(TS 3.8.3 Condo E)TS 3.8.3: Page 3 of 5 RESULTS: STANDARDS: (CIRCLE)Determines

that of the 9 given DG parameters, one makes the IB DG S I U inoperable

due to usable Fuel Level.This TS also requires immediately

declaring the IB DG inoperable.

1/2A IC 1B Diesel Fuel Oil 25,500 gals 25,500 gals 20,350 gals storage tank contents Inoperable (TS 3.8.3 Cond F.&TS 3.8.1)Lube Oil inventory 248 gals 183 gals 255 gals Starting Air receiver 415 psig 240 psig 425 psig pressures STOP TIME Terminate when all initial conditions

have been evaluated.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*)before the element number.

HL T-31 ADMIN exam A.1.1 SRO Page 4 of 5 2.KIA: G2.1.10 SRO 3.9 GENERAL TOOLS AND EQUIPMENT:

Provide: 1.Marked up STP-35.1 2.Marked up STP-I0.4 3.Marked up STP-15.0 4.Technical Specifications

&Basis for TS 3.8.1&3.8.3 COMMENTS:

HLT-31 ADMIN exam A.1.1 SRO Page 5 of 5 CONDITIONS

When I tell you to begin, you are to determine if Mode 4 entry is allowed.IF mode 4 entry is prohibited, identify which conditions

preclude Mode 4 entry.eVIew ormo e s as een comp.e e excep or w IC ave parame ers I 1/2A 1C 1B Diesel Fuel Oil 25,500 gals 25,500 gals 20,350 gals storage tank contents Lube Oil inventory 248 gals 183 gals 255 gals Starting Air receiver 415 psig 240 psig 425 psig pressures a.Unit 1 is in Mode 5.b.You are the Shift Support Supervisor.

You are to complete filling out STP-35.1 and determine if Mode 4 entry is allowed.If any conditions

preclude Mode 4 entry, then identify all conditions

that preclude Mode 4 entry.c.Shift turnover and shift brief has just been completed.

1.STP-35.1, step 5.3, is in progress reviewing requirements

for Mode 4 entry.2.STP-1.0 has been performed 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ago for mode 4.3.All STPs have been reviewed per FNP-1-STP-35.1E

with exceptions

noted on coversheet.

4.Taggout review is complete sat.5.All applicable

signatures

and initials have been completed in STP-35.1 except on the pages provided.6R*£d4 LCO h bitdt£DG h*hht l*sted:

Southern Nuclear Operating Company, Inc.Post Office Drawer 470 Ashford, Alabama 36312 Tel 334,899.5156

Fax 334,814.4661

1/4/2008 Mr.Frank Ehrhardt United States Nuclear Regulatory

Commission

Sam Nunn Atlanta Federal Center 61 Forsyth Street SW, Suite 23T85 Atlanta, Georgia 30303-8931

Dear Mr.Ehrhardt, FNP-2008-002-

TRN Energy to Serve lOur World slV1 Enclosed is our Post-Written

Examination

submittal of examination

grade sheets, post-exam comments, and other materials.

The ES-201 Form, Examination

Security Agreement, is in the process of being signed off as personnel become available.

The ES-201 Form will be set at a later date as soon as all required signatures

are obtained.Enclosed you will find the following forms and materials for the NRC Written examination

administered

on 12-21-2007

at Farley Nuclear Plant.Hard Copy: 1)Eleven,5 SRO&6 RO, exam grade sheets for electronic

scanning in LXR software (scantron sheets)2)Exam cover sheets signed by Applicants

3)Preliminary

grades 4)ES-403-1, Written Examination

Grading Quality Checklist 5)ES-401-6, Written Examination

Quality Checklist (resubmitted

original due to some inadvertently

omitted initials on previously

submitted form)6)Written Exam seating chart 7)List of Questions and replies during exam 8)Post exam comments for potential Key changes Question 95, G2.1.6, is security related and must be withheld from public disclosure.

The remainder of this material should be withheld from public disclosure

until after the examination

grading is complete.If you have any questions, please contact Charles V.(Vince)Richter at (334)814-4758.nmn onna M.Christiansen

OPS Training Supervisor

Enclosure CVR/DMC cc: File

Farley NRC Written exam Applicant questions and answers during exam, 12-21-2007

Examination

proctors: Vince Richter&Gary Ohmstede NRC chief examiner available by telephone:

Frank J.Ehrhardt[bracketed

text indicates post exam comments NOT communicated

by or to any applicants

during the exam]LJ Applicant I Question/comment

I Answer I 17 Newell Does"the BKR Panel" mean the lA 120V Yes Vital panel?17 Pickens Can I assume that RCP BKR ind is lost?[After phone call with chief examiner]:

Assume all systems are aligned per normal actual plant conditions

16 Rose LT-459 Failed low, how low did it fail?As low as it can fail.36 Newell R-15A is at midscale, is it stable at mid scale Take the statement at to start with?face value 25 Rose Valves are stated to be closed, can I assume Take statements

at face the SI signal to the valves has been disabled?value.Everything

that has been done is stated or implied in the question 77 Payne Desire documentation

of comment for this We'll document your question because Payne thought that A was comment.most correct and was going to choose it, but thought the 2 nd part of A was not correct.The[There was no A choice stated that subcooling

being too low problem found with was the reason, but the real reason should be this question or choice that a LOCA is in progress.A]86 Payne Assuming MSIV Auto closure has occurred, We'll document your since an assumption

must be made to assumption.

distinguish

between A&D[This assumption

was not necessary.

Stem conditions

indicated that an auto MSIV closure had occurred on low steam pressure]89 Payne Can I assume that"Releases can continue" Yes.means only future releases but not the current release?Page 10f2

Farley NRC Written exam Applicant questions and answers during exam, 12-21-2007

Examination

proctors: Vince Richter&Gary Ohmstede NRC chief examiner available by telephone:

Frank J.Ehrhardt[bracketed

text indicates post exam comments NOT communicated

by or to any applicants

during the exam]17 NaIl Does this question ask the BKR Position Answer the question as between the two times 1000&1010?written.[The time of the question was clearly stated in the stem].90 Carrol Does placing B TRN of SW on service mean The statement means placing C SW Pump on B train?what it says.87 Szollosi The high alarm light is stated to be NOT lit.Answer based on Was the high alarm light ever lit just previous conditions

given.to these conditions?

55 Prichett Is the loss of A train SW just U-2, or is it a Unit 2 only.total loss of SW?82 Taylor What time is the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> in choice"C" Answer the question as referenced

to of the several times in the stem?written.22 Carrol Confused about what A and B choices[No response actually meant.required][Ended up without asking a question or making a comment.Applicant talkedthroughit while trying to explain his confusion and said: "I guess 1 answered my own question"]

36 Prichett Does this mean SJAE Filtration

is on service It means what it says.when the Rx Trips?32 Carrol What is RCS Press?Did Letdown operate?This is as expected during an ATWT event.74 Wilhoit Is the location in Choice"B" really what it It means what it says.means?Page 2 of2

P",'()--;)l- Se.CL{t'f"rFRONT (Courtney Rose Mike Wilhoit Rob Szollosy Josh Pritchett J ash Carroll Matt NaIl Tracey Newell Taylor Joseph Matt Pickens Brannon Payne Steve Lee

Farley NRC Written Exam 12-21-2007

comments Question 32, 029 EKl.Ol References:

FRP-S.l Given the following:

• • • • • • • An ATWT has occurred on Unit 2 during coastdown prior to entering a refueling outage.The crew is performing

actions of FRP-S.1, Response to Nuclear Power Generation/ATWT.

An operator has been dispatched

to trip the reactor locally.Attempts to establish Emergency Boration have been unsuccessful.

Reactor power indicates 6%.Intermediate

Range Startup rate is slightly positive.The RCS temperature

is slowly rising.Which ONE of the following describes the actions required lAW FRP-S.1?A.[Originally

identified

as Correct]Allow the RCS to heat up, and continue attempts to place the reactor in a subcritical

condition.

B.[Also Correct]Allow the RCS to heat up, and open one PORV as necessary to maintain pressurizer

pressure less than 2135 psig to increase charging flow.c.&D[Incorrect, no change toC&0]Comment: Both'B'and'A'should be accepted as correct, since the first parts of both are the same, and the second part of B is a subset of A.FRP-S.1 has procedure steps for continuing

attempts to place the reactor in a sub critical condition which include, during establishing

emergency boration, step 4.5 RNO"open one PORV as necessary to maintain pressurizer

pressure less than 2135 psig to increase charging flow." The words"as necessary" in the second part of'B'make it correct.Even though there is no reason to believe that the PORVs would not open and control pressure automatically, in which case it would not be necessary to open the PORVs manually, it is still true that"opening PORVs as necessary" is required.Page 1 of 3

Farley NRC Written Exam 12-21-2007

comments Question 90, 076 G2.1.2 References:

SOP-24.0, AOP-IO.O, ARP-l.l Window AE4 Given the following:

-Unit 2 is at 1 00%power withlA" Train on service.-At 1200 on 11/7/2007, 2E Service Water pump tripped and"B" Train SW was declared INOPERABLE.

Which ONE of the following describes the Technical Specification

REQUIRED ACTION lAW 3.7.8, Service Water System, and the action required to make"B" Train Service Water OPERABLE?A.[Originally

identified

as Correct]-Immediately

declare the DG supported by Train"B" Service Water INOPERABLE.

-Place"B" Train of SW on service and align 2C SW pump to auto start for 2E SW pump lAW SOP-24.0, Service Water System.B.[Also Correct]-Immediately

declare the OG supported by Train"B" Service Water INOPERABLE.

-Align 2C SW pump to auto start for 2E SW pump lAW AOP-1 0.0, Loss of Service Water.c.&D[Incorrect, no change toC&0]Comment: Both'B'and'A'should be accepted as correct, since the first parts of both are the same, and the second parts of both provide procedurally

correct paths to obtain the same result.They would both result in the B Train Service Water Operable as the question asks.The differences

between choices'A'&'B'are: 1)'A'states a more complete description

of the action of"placing C SW pump on the B Train and then aligning it to auto start for E", but the shortened description

in'B'"Align 2C SW pump to auto start for 2E" includes all the actions to perform this by the procedure:

SOP-24.0.IF both trains of SW were>60 psig after AOP-10.0 directed starting the 2C SW pump, the ARP would direct SOP-24.0 and'A'-is the'correct choice.2)'A'states the alignment is performed per SOP-24 which is correct.Even though, per'B'choice, AOP-10.0 does not directly provide guidance for aligning the 2C SW Pump for E, AOP-10 does direct swapping per AOP-24.0 later in the procedure.

AOP-10.0 is entered and performed, and if SW pressure is not>60 psig in both Trains, AOP-10.0 will be continued to the point of directing 2C SW Pump swap and alignment to auto start for 2E per SOP-24.0.SW Pressure is not given in the question stem, so knowledge of the procedure led some to choose'B'because the stem did not preclude AOP-10 directing the alignment.

The simulator is modeled for SW pressure being>60 psig after starting 2C SW pump, but in tile plant, it may be<60 psig in otlleI plant COllditiolIS

than the simulator modeling (e.g.heat of the summer with all SW cooling valves throttled max open).Page 20f3

Farley NRC Written Exam 12-21-2007

comments Question 100, G2.4.44 References:

EIP-9.0 A Site Area Emergency was declared 35 minutes ago.Subsequently, conditions

have degraded and a General Emergency classification

needs to be declared.When upgrading to the General Emergency classification, which one of the following contains ONLY required actions lAW FNP-O-EIP-9.0, Emergency Actions?A.&D.[Incorrect, No change]B.[Previously

inadvertently

identified

in LXR as correct]*Sounding of the plant emergency alarm.*Notify Alabama and Georgia of the status of the unaffected

Unit.c.[Should have been identified

in LXR as correct]*Notify Alabama and Georgia of Protective

Action Recommendations.

• Announce needed evacuation

instructions

to plant personnel.

Comment: 'B'is incorrect because the plant emergency alarm has already been actuated for the Site Area Emergency.

The alarm is not directed to be sounded again for the General Emergency.

Also, the second part is incorrect because the unaffected

Unit status is not required for the initial General Emergency notification.

'C'is correct, and should be accepted as the only correct answer, since the PARs are required for both Alabama and Georgia for theGeneralEmergency, and the procedure requires the announcement

of needed evacuation

instructions

to plant personnel.

Page 3 of3

Farley Nuclear Plant 2006-301 SRO Inital Exam 32.029 EKl.Ol 001 Given the following:

• An ATWT has occurred on Unit 2 during coastdown prior to entering a refueling outage.*The crew is performing

actions of FRP-S.1, Response to Nuclear Power Generation!

A TWT.*An operatorhasbeen dispatched

to trip the reactor locally.*Attempts to establish Emergency Boration have been unsuccessful.

• Reactor power indicates 6%.*Intermediate

Range Startup rate is slightly positive.*The RCS temperature

is slowly rising.Which ONE of the following describes the actions required lAW FRP-S.1?Allow the ReS to heat up, and continue attempts to place the reactor in a subcritical

condition.

B.Allow the RCS to heat up, and open one PORV as necessary to maintain pressurizer

pressure less than 2135 psig to increase charging flow.C.Stop the RCS heatup by increasing

AFW flow to greater than 700 gpm, and verify dilution paths isolated.D.Stop the RCS heatup by dumping steam to the main condenser, and continue attempts to place the reactor in a subcritical

condition.

FRP-S.1 version 25 17 Continue emergency boration.17 Perform the following.

17.1 Determine if moderator temperature

coefficient

positive or negative.[]Core Physics Curve 5 17.2 IF moderator temperature

coefficient

negative, THEN allow ReS to heat up.A.correct.During coastdown at EOl, MTC is negative under all conditions.

Do not leave FRP-S.1 until power below 5°A>.IF power was to be>%5 or a positive SUR on the IR, then in addition to continuing

the emergency boration, if the MTC is negative, then the RCS would be allowed to HU to add positive reactivity

to the core and help shut it down.B.incorrect The RCS is allowed to heatup, but the PORvs are not cycled to maintain pressure less than 2135 psig unless pressure is>2335 psig.C.incorrect because S.1 does not have the AFW flow to be>700 gpm for this reason, but does have an RNO step to increase AFW flow to 700 gpm if SGWls are not>31%D.incorrect RCS temperature

is not stabilized, it is allowed to rise.

Farley Nuclear Plant 2006-301 SRO Inital Exam 029 Anticipated

Transient Without Scram (ATWS)EK1.01 Knowledge of the operational

implications

of the following concepts as they apply to theATW8: Reactor nucleonics

and thermo-hydraulics

behavior Question Number: 46 Tier 1 Group 1 Importance

Rating: R02.8 Technical Reference:

FRP-S.1 Proposed references

to be provided to applicants

during examination:

None Learning Objective:

10 CFR Part 55 Content: 41.1 0 Comments: This meets the KA in that this tests the operational

implications

during an A TWT and the effects that we would take if the reactor was still critical after emergency boration and rods going in what would happen temperature

wise, ie.thermo-hydralic

behavior.

FNP-I-FRP-S.l

4-20-2007 Revision 25 FARLEY NUCLEAR PLANT FUNCTION RESTORATION

PROCEDURE FNP-I-FRP-S.l

RESPONSE TO NUCLEAR POWER GENERATION/ATWT

PROCEDURE USAGE REQUIREMENTS-per

FNP-O-AP-6

SECTIONS Continuous

Use Remainder of Procedure Reference Use Steps 1-2 Information

Use S A F E T Y R E L A T E D Approved: Jim L.Hunter (for)Operations

Manager Date Issued: 04/23/07

FNP-1-FRP-S.1

'.}..1..\t::l:.J:t.Ji.... RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Table of Contents Revision 25 Procedure Contains Number of Pages Body 19 Attachment

1 8 Attachment

2 8 Page 1 of 1

FNP-1-FRP-S.1

A.Purpose

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jilL..,1;:1..."':i...RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Revision 25 This procedure provides actions to add negative reactivity

to a core which is observed to be critical when expected to be shutdown.B.Symptoms or Entry Conditions

I.This procedure is entered when reactor trip is not verified and manual trip is not effective;

from the following:

a.FNP-1-EEP-O, REACTOR TRIP OR SAFETY INJECTION, step 1 II.This procedure is entered from the Subcriticality

Critical Safety Function Status Tree on either a Red or Orange condition.

Page 1 of 19

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Revision 25 Step 11 Action/Expected

Response Response NOT Obtained**************************************************************************************

CAUTION: rCA]RCPs should NOT be tripped with reactor power GREATER THAN 5%.**************************************************************************************

NOTE: Steps 1 and 2 are IMMEDIATE ACTION steps.1 Verify reactor-TRIPPED.RX TRIP ACTUATION[]AB to TRIP 1 Perform the following.

1.1 Trip CRDM MG set supply breakers.lA(IB)MG SET SUPP BKR[J NICIIE005A

[J NICIIE005B

1.2 IF reactor still NOT tripped, THEN perform the following.

• Insert control rods in manual control.OR*Verify rods insert in AUTO at greater than 48 steps per minute.1.2.1 Dispatch an operator to locally trip the reactor trip and bypass breakers.___Page Completed Page 2 of 19

FNP-1-FRP-S.1

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Revision 25 Step 11 Action/Expected

Response Response NOT Obtained NOTE: The DEB Valve Test Display may be used for alternate indication

of turbine stop valve and governor valve position.--2 Check turbine-TRIPPED.[]TSLB2 14-1 lit[]TSLB2 14-2 lit[]TSLB2 14-3 lit[]TSLB2 14-4 lit 2 Perform the following.

2.1 Place MAIN TURB EMERG TRIP switch to TRIP for at least 5 seconds.2.2 IF turbine NOT tripped, THEN close GVs.2.2.1 Reduce GV position demand signal to zero from DEH panel.[J TURBINE MANUAL depressed[J GV CLOSE depressed[J FAST ACTION depressed Step 2 continued on next page.___Page Completed Page 3 of 19

FNP-I-FRP-S.l

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Revision 25 Step Action/Expected

Response II I I--3 Verify AFW pumps-RUNNING.3.1 MDAFWPs-RUNNING[J lA amps>0[J IB amps>0 3.2 TDAFWP-RUNNING IF NECESSARY*TDAFWP STM SUPP FROM IB(IC)SG[]MLB-4 1-3 lit[]MLB-4 2-3 lit[]MLB-4 3-3 lit*TDAFWP SPEED[]SI 3411A>3900 rpm*TDAFWP SPEED CONT[]SIC 3405 at 100%Response NOT Obtained NOTE:*2500 gallons of emergency boration is required for each control rod not fully inserted, up to a maximum of 17,309 gallons.*[CA]Emergency boration should continue until an adequate shutdown margin is established.

4 4.1 Initiate Emergency Boration ofthe Res.Verify at least one CRG PUMPRUNNING.Step 4 continued on next page.___Page Completed Page 5 of 19

FNP-I-FRP-S.l

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Revision 25 Step 11 Action/Expected

Response Response NOT Obtained 4.2 Start a boric acid transfer pump.BATP[J lA[J 1B 4.3 Align normal emergency boration.EMERG BORATE TO CRG PUMP SUCT[J Q1E21MOV8104

open 4.2 Perform the following.

4.2.1 Align charging pump suction to RWST.RWST TO CRG PUMP[]QIE21LCVl15B

open[J Q1E21LCVl15D

open VCT OUTLET ISO[J Q1E21LCVl15C

closed[]Q1E21LCVl15E

closed 4.2.2 Proceed to step 4.4.4.3 Perform the following.

• Align charging pump suction to RWST.RWST TO CRG PUMP[]Q1E21LCVl15B

open[J Q1E21LCVl15D

open VCT OUTLET ISO[J QIE21LCVl15C

closed[J Q1E21LCV115E

closed*Align manual emergency boration flow path.BORIC ACID TO BLENDER[J QIE21FCVl13A

open MAN EMERG BORATION[J Q1E21V185 open (100 ft, AUX BLDG rad side chemical mixing tank area)Step 4 continued on next page.___Page Completed Page 6 of 19

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Revision 25 Step 11 Action/Expected

Response Response NOT Obtained 4.4 Establish adequate letdown.4.4.1 Verify 45 GPM letdown orifice-IN SERVICE.LTDN ORIF ISO 45 GPM[J Q1E21HV8149A

open 4.4.2 Verify one 60 GPM letdown orifice-IN SERVICE.LTDN ORIF ISO 60 GPM[J Q1E21HV8149B

open[J Q1E21HV8149C

open 4.5 Check pressurizer

pressure LESS THAN 2335 psig.4.6 Establish adequate charging flow.*IF boration is from boric acid storage tank, THEN verify charging flowGREATER THAN 40 GPM.*IF boration is from the RWST, THEN verify charging flowGREATER THAN 92 GPM.4.5 Verify PRZR PORVs and PRZR PORV ISOs-OPEN.IF NOT,.THEN open PRZR PORVs and PORV ISOs as necessary until pressurizer

pressure less than 2135 psig.CaJetVd'-([f:0)'\Step 4 continued on next page.___Page Completed Page 7 of 19

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Revision 25 Step 11 Action/Expected

Response Response NOT Obtained 4.7 Verify emergency boration flow adequate.4.7.1 IF normal emergency boration flow path aligned, THEN check emergency boration flow greater than 30 GPM.BORIC ACID EMERG BORATE[J FI 110 4.7.2 IF manual emergency boration flow path aligned, THEN check boric acid flow greater than 30 GPM.MAKEUP FLOW TO CHG/VCT[J BA FI 113 4.7.3 IF boration is from the RWST, THEN verify charging flowGREATER THAN 92 GPM.___Page Completed Page 8 of 19

FNP-I-FRP-S.l

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Revision 25 Step 11 5 Action/Expected

Response Verify containment

ventilation

isolation.

Response NOT Obtained 5.1 Verify containment

purge dampers-CLOSED.[]3197[]3198D[]3198C[]3196[]3198A[]3198B 5.2 Verify containment

mini purge dampers-CLOSED.CTMT PURGE DMPRS MINI-2866C

&2867C FULL-3198A

&3198D[]2866C[]2867C CTMT PURGE DMPRS MINI-2866D

&2867D FULL-3196&3197 BOTH-3198B

&3198C[]2866D[]2867D 5.3 Stop MINI PURGE SUPP/EXH FAN.6 Check SI actuated.6.1 Check any SI actuated indication.

BYP&PERMISSIVE

SAFETY INJECTION[]ACTUATED status light lit[]MLB-l 1-1 lit[]MLB-1 11-1 lit 6.2 Initiate ATTACHMENT

1, AUTUMATiC

INJECTIUN VERIFICATION.

___Page Completed 6 5.1 Manually close dampers.5.2 Manually close dampers.[CA]IF an SI signal is actuated during this procedure, THEN initiate ATTACHMENT

1, AUTOMATIC SAFETY INJECTION VERIFICATION.

Page 9 of 19

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Revision 25 Step Il 7 Action/Expected

Response Check the following trips.Response NOT Obtained 7.1 Verify all reactor trip and reactor trip bypass breakersOPEN.7.2 Check turbine-TRIPPED.[]TSLB2 14-1 lit[]TSLB2 14-2 lit[]TSLB2 14-3 lit[]TSLB2 14-4 lit___Page Completed Page 10 of 19 7.1 Locally open the reactor trip and reactor trip bypass breakers.7.2 Locally place turbine overspeed lever to TRIP for at least 5 seconds.(189 ft, TURB BLDG)

FNP-I-FRP-S.l

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Revision 25 Step II Action/Expected

Response Response NOT Obtained**************************************************************************************

CAUTION: Emergency boration should be continued until adequate shutdown margin is established.

NOTE: Step 8 is a continuing

action step.8[CAl Check if reactor still critical.*Check power range indication

-GREATER THAN OR EQUAL TO 5%.PRl(2,3,4)

PERCENT FULL POWER[J NI 41B[J NI 42B[J NI 43B[J NI 44B*Check any intermediate

range startup rate-POSITIVE.IRl(2)siu RATE[J NI 35D[J NI 36D 8 Go to procedure and step in effect.___Page Completed Page 11 of 19

FNP-1-FRP-S.1

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Revision 25 Step 11 Action/Expected

Response Response NOT Obtained 9 Monitor CST level.9.1[CA]Check CST level greater than 5.3 ft.CST LVL[]LI 4132A[]LI 4132B 9.2 Align makeup to the CST from water treatment plant OR demin water system using FNP-1-S0P-5.0, DEMINERALIZED

MAKEUP WATER SYSTEM, as necessary.

10 Check SG levels.10.1 Check at least one SG narrow range level-GREATER THAN 31%{48%}.9.1 Align AFW pumps suction to SW using FNP-1-S0P-22.0, AUXILIARY FEEDWATER SYSTEM.10.1 Perform the following.

10.1.1 Verify total AFW flow greater than 700 gpm.AFW FLOW TO 1A(lB,lC)SG[]FI 3229A[]FI 3229B[]FI 3229C AFW TOTAL FLOW[]FI 3229 Step 10 continued on next page.___Page Completed Page 12 of 19

FNP-1-FRP-S.1

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Revision 25 Step 11 Action/Expected

Response Response NOT Obtained I I 10.1.2 Verify AFW valves open.MDAFWP TO 1A(lB,lC)SG FLOW CONT[]HIC 3227AA[]HIC 3227BA[]HIC 3227CA TDAFWP TO 1A(lB,lC)SG FLOW CONT[]HIC 3228AA[]HIC 3228BA[]HIC 3228CA AFW TO 1A(lB,lC)SG STOP VLV[]'Q1N23MOV3350A[]Q1N23MOV3350B

[]Q1N23MOV3350C

MDAFWP TO 1A(lB,lC)SG ISO (BOP)[J Q1N23MOV3764A[]Q1N23MOV3764D[]Q1N23MOV3764F[]Q1N23MOV3764E[]Q1N23MOV3764B

[]Q1N23MOV3764C

Step 10 continued on next page.___Page Completed Page 13 of 19

FNP-1-FRP-S.1

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Revision 25 Step 11 Action/Expected

Response Response NOT Obtained 10.2[CA]WHEN SG narrow range level greater than 31%{48%}, THEN maintain SG narrow range level 31%-65%{48%-65%}.

10.2.1 Control MDAFWP flow.MDAFWP FCV 3227 RESET[]A TRN reset[]B TRN reset MDAFWP TO 1A/1B/1C SG B TRN[]FCV 3227 in MOD SG 1A 1B 1C MDAFWP TO 1A(lB,lC)SG Q1N23HV[]3227A[]3227B[]3227C in MOD in MOD in MOD MDAFWP TO 1A(lB,lC)SG FLOW CONT HIC[]3227AA[]3227BA[]3227CA adjusted adjusted adjusted Step 10 continued on next page.___Page Completed Page 14 of 19

FNP-1-FRP-S.1

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Revision 25 Step Action/Expected

Response Response NOT Obtained 11 I I I 10.2.2 Control TDAFWP flow.TDAFWP FCV 3228[]RESET reset TDAFWP SPEED CONT[]SIC 3405 adjusted SG TDAFWP TO 1A(lB,lC)SG Q1N23HV 1A[]322 8A in MOD 1B[]3228B in MOD 1C[]3228C in MOD TDAFWP TO 1A(lB,lC)SG FLOW CONT HIC[]3228AA[]3228BA[]3228CA adjusted adjusted adjusted_11 Verify dilution paths isolated.11.1 Isolate RMW to boric acid blender.RMW TO BLENDER[]Q1E21FCVl14B

closed 11.2 Notify Chemistry to secure the zinc addition system (ZAS).11.3 Verify RMW supp iso to CHG pump suction locked closed (key#Z-58).[]Q1E21V212 locked closed (100'elev.AUX BLDG BIT area at suction of CRG pumps)___Page Completed Page 15 of 19 11.1 Locally isolate RMW to CVCS.RMW TO CVCS ISO[]Q1E21V233 closed (100'elev.AUX BLDG above hydro test pump)

FNP-I-FRP-S.l

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Revision 25 Step 11 12 Action/Expected

Response Check for reactivity

addition from UNCONTROLLED

RCS cooldown: 12 Response NOT Obtained Perform the following:

• Check RCS cold leg temperature

-DECREASING

IN AN UNCONTROLLED

MANNER.RCS COLD LEG TEMP[J TR 410*Check any SG pressureFALLING IN AN UNCONTROLLED

MANNER OR LESS THAN 50 psig.12.1 Stop any CONTROLLED

cooldown.12.2 Proceed to step 15._13_14 Check main steam line isolation and bypass valves-CLOSED.Check SGs not faulted.14.1 Check no SG pressure-FALLING IN AN UNCONTROLLED

MANNER OR LESS THAN 50 psig.13 Close the main steam line isolation and bypass valves.lA(IB,IC)SG MSIV-TRIP[J QINIIHV3369A

[J QINIIHV3369B

[J QINIIHV3369C

[J QINIIHV3370A

[J QINIIHV3370B

[J QINIIHV3370C

lA(IB,IC)SG MSIV-BYPASS[J QINIIHV3368A

[J QINIIHV3368B

[J QINIIHV3368C

[J QINIIHV3976A

[J QINIIHV3976B

[J QINIIHV3976C

14.1 Isolate faulted SG(s)using ATTACHMENT

2._15 Check core exit TiCs-LESS THAN 1200°F.___Page Completed 15 IF fifth hottest core exit Tic greater than 1200°F AND rising, rT1T.,.,..., T ,...,...T-n 1 rt nn n 1.LlllJl\l gu LU£l\lr.L 0h.\...JI\.\J.L, SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE.Page 16 of 19

FNP-I-FRP-S.l

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Revision 25 Step 11 Action/Expected

Response Response NOT Obtained**************************************************************************************

CAUTION: Emergency boration should be continued until adequate shutdown margin is established.

_16 17 Check if reactor still critical.*Check power range indication

-GREATER THAN OR EQUAL TO 5%.PRl(2,3,4)

PERCENT FULL POWER[J NI 41B[J NI 42B[J NI 43B[J NI 44B*Check any intermediate

range startup rate-POSITIVE.IRl(2)siu RATE[J NI 35D[J NI 36D Continue emergency boration.16 17 Go to procedure and step in effect.Perform the following.

17.1 Determine if moderator temperature

coefficient

positive or negative.[J Core Physics Curve 5 17.2 IF moderator temperature

coefficient

negative, THEN allow RCS to heat up.___Page Completed Page 17 of 19

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Revision 25 Step Il Action/Expected

Response Response NOT Obtained NOTE: 18 Actions of other Function Restoration

Procedures

in effect which will not add positive reactivity

to the core may be performed while efforts to return the core to a subcritical

condition continue.Return to step 4.-END-Page 18 of 19

FNP-1-FRP-S.1

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CONTINUOUS

ACTION Revision 25 D D 1 CAUTION[CA]RCPs should NOT be tripped with reactor power GREATER THAN 5%.4 NOTE[CA]Emergency boration should continue until an adequate shutdown margin is established.

D 6 6[R][CA]IF an SI signal is actuated during this procedure, THEN initiate ATTACHMENT

1, AUTOMATIC SAFETY INJECTION VERIFICATION.

D D D 8[CA]Check if reactor still critical.9 9.1[CA]Check CST level greater than 5.3 ft.10 10.2[CA]WHEN SG narrow range level greater than 31%{48%}, THEN maintain SG narrow range level 31%-65%{48%-65%}.

Page 19 of 19

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Revision 25 Step Il Action/Expected

Response ATTACHMENT

1 Response NOT Obtained AUTOMATIC SAFETY INJECTION VERIFICATION

CAUTION: Diesel generator damage may occur if all running diesels are not supplied with service water within three minutes.**************************************************************************************

1 Check power to 4160 V ESF busses.1.1 4160 V ESF busses-AT LEAST ONE ENERGIZED*A Train (F&K)power available lights lit*B Train (G&L)power available lights lit 1.2 4160 V ESF busses-BOTH ENERGIZED[J A Train (F&K)power available lights lit[J B Train (G&L)power available lights lit 1.3 Verify operating diesel generators

are being supplied from at least one SW pump.1.2 Try to restore power to deenergized

4160 V ESF bus as time permits while continuing

with the remainder of this procedure.

1.3 IF service water flow cannot be readily restored to a running diesel generator THEN secure the diesel generator using operator aid located on EPB.___Page Completed Page 1 of 8

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Revision 25 Step 11 Action/Expected

Response ATTACHMENT

1 Response NOT Obtained 2 Check SI Status.2.1 Check any SI actuated indication.

BYP&PERMISSIVE

SAFETY INJECTION[J ACTUATED status light lit[J MLB-l 1-1 lit[J MLB-l 11-1 lit 2.2 Verify both trains ofACTUATED.[J MLBI 1-1 AND MLBI 11-1 lit 3 Verify main feedwater status.3.1 Verify main feedwater flow control and bypass valvesCLOSED.lA(IB,IC)SG FW FLOW[J FCV 478[]FCV 488[J FCV 498 lA(IB,IC)SG FW BYP FLOW[J FCV 479[]FCV 489[J FCV 499 3.2 Verify both steam generator feed pumps-TRIPPED.3.3 Verify SG blowdown-ISOLATED.lA (IB, lC)SGBD ISO[]QIG24HV7614A

closed r 1 (\1 (")/.U1 T 7 h 1/I"R n 1 r..rc r..LJ

.........'-J......L.LJ[J QIG24HV7614C

closed 2.2 Manually actuate SI.3.1 Verify main feedwater stop valves closed.MAIN FW TO lA(IB,IC)SG STOP VLV[J QIN21MOV3232A

[J QIN21MOV3232B

[J QIN21MOV3232C

3.2 Stop both EH PUMPs.Step 3 continued on next page.___Page Completed Page 2 of 8

FNP-1-FRP-S.1

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Revision 25 Step 11 Action/Expected

Response ATTACHMENT

1 Response NOT Obtained 3.4 Verify SG blowdown sample ISOLATED MLB lights lit.1A(lB,lC)SGBD SAMPLE ISO[]MLB4 6-4 lit Q1P15HV3328

closed[J MLB4 7-4 lit Q1P15HV3329

closed[]MLB4 8-4 lit Q1P15HV3330

closed 3.4 Locally verify SGBD sampleisolated (BOP).STEAM GEN 1A(lB,lC)SAMPLE ISO[J Q1P15HV3328

closed[J Q1P15HV3329

closed[J Q1P15HV3330

closed OR Locally verify SGBDisolated (PRIP).STEAM GEN 1A(lB,lC)SAMPLE

ISO 4 Verify PHASE A CTMT ISO.4.1 Verify PHASE A CTMT ISOACTUATED.[J MLB-2 1-1 lit[J MLB-2 11-1 lit[J Q1P15HV3179C

[J Q1P15HV3180C

[J Q1P15HV3181C

closed closed closed NOTE: The turbine building SW isolation valves Q1P16V515, 517, 514 and 516 will take approximately

two minutes to fully stroke closed.4.2 Check all MLB-2 lights-LIT.-5 Verify one CRG PUMP in each train-STARTED.[]A train (lA or 1B)amps>0[]B train (lC or 1B)amps>0 4.2 Verify proper PHASE A CTMT ISO alignment.

___Page Completed Page 3 of 8

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Revision 25 Step 11 6 7 Action/Expected

Response ATTACHMENT

1 Verify RHR PUMPs-STARTED.RHR PUMP[J lA amps>0[J IB amps>0 Verify each train of CCWSTARTED.Response NOT Obtained_8 7.1 Verify one CCW PUMP in each train-STARTED.A train HX lC or IB CCW FLOW[J FI 3043CA>0 gpm OR[J FI 3043BA>0 gpm B train HX lA or IB CCW FLOW[J FI 3043AA>0 gpm OR[J FI 3043BA>0 gpm 7.2 Verify SW flow to associated

CCW HX's.SW FROM lA(IB, Ie)CCW HX[J QIP16FI3009AA

>0 gpm[J QIP16FI3009BA

>0 gpm[J QIP16FI3009CA

>0 gpm Verify each SW train-HAS TWO SW PUMPs STARTED.[J A train (IA,IB or lC)[J B train (ID,IE or lC)7.2 Modulate open SW to the associated

CCW HX's.[J QIP16FV3009A

[J QIP16FV3009B

[J QIP16FV3009C

___Page Completed Page 4 of 8

FNP-1-FRP-S.1

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J:L RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Revision 25 Step Il 9 Action/Expected

Response ATTACHMENT

1 Verify containment

fan cooler alignment.

Response NOT Obtained 9.1 Verify at least one containment

fan cooler per train-STARTED IN SLOW SPEED.CTMT CLR FAN SLOW SPEED*A train[J 1A[J 1B*B train[J1C[J 1D 9.2 Verify associated

emergency service water outlet valvesOPEN.EMERG SW FROM 1A(lB,lC,lD)

CTMT CLR[J Q1P16MOV3024A

[J Q1P16MOV3024B

[J Q1P16MOV3024C

[J Q1P16MOV3024D

___Page Completed Page 5 of 8

FNP-I-FRP-S.l

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Revision 25 Step 11 Action/Expected

Response ATTACHMENT

1 Response NOT Obtained-10 Check no main steam line 10 Perform the following.

isolation actuation signal present.10.1 Verify main steam line isolation and bypass valves closed.Signal SetDoint Coincidence

TSLB TSLB4 lA(IB,IC)SG LO 19-2 MSIV-TRIP SG PRESS<585 psig 2/3 19-3[]QINIIHV3369A

19-4[]QINIIHV3369B

TSLB4[]QINIIHV3369C

HI 1/2 16-3 16-4[J QINIIHV3370A

STEAM>40%ON 17-3 17-4[]QINIIHV3370B

FLOW 2/3 18-3 18-4[]QINIIHV3370C

AND TSLB2 lA(IB,IC)SG 10-1 MSIV-BYP LO-LO<543 0 F 2/3 10-2[]QINIIHV3368A

TAVG 10-3[]QINIIHV3368B

TSLBI[]QINIIHV3368C

HI-HI 2-2[]QINIIHV3976A

CTMT>16.2 psig 2/3 2-3[]QINIIHV3976B

PRESS 2-4[]QINIIHV3976C

10.2 IF any main steam isolation valve open, THEN place the associated

test switch in the TEST position.SG lA IB lC lA(IB,IC)SG MSIV-TEST QINIIHV[J 3369AI[J 3369BI[J 3369CI 70A 70B 70C___Page Completed Page 6 of 8

FNP-1-FRP-S.1

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J::..RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Revision 25 Step Il Action/Expected

Response ATTACHMENT

1 Response NOT Obtained**************************************************************************************

CAUTION: RCPs should NOT be tripped with reactor power GREATER THAN 5%.**************************************************************************************

NOTE: Step 11 is a continuing

action step while in this procedure.

11 Check containment

pressureHAS REMAINED LESS THAN 27 psig.CTMT PRESS[J PR 950 11 Perform the following.

11.1 Verify PHASE B CTMT ISOACTUATED.[]MLB-3 1-1 lit[]MLB-3 6-1 lit 11.2 Stop all RCPs.RCP[]1A[J 1B[]1C 11.3 Verify PHASE B CTMT ISO alignment.

11.3.1 Check All MLB-3 lights lit.11.3.2 IF any MLB-3 light NOT lit, THEN verify proper PHASE B CTMT ISO alignment.

___Page Completed Step 11 continued on next page.Page 7 of 8

FNP-1-FRP-S.1

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Revision 25 Step 11 Action/Expected

Response ATTACHMENT

1 Response NOT Obtained 11.4 Check containment

spray.11.4.1 Check containment

spray flow in both trains greater than 0 gpm.CS FLOW[J FI 958A[J FI 958B 11.4.2 IF containment

spray flow in both trains NOT greater than 0 gpm, THEN verify containment

spray pump suction valves open.RWST TO 1A(lB)CS PUMP[J Q1E13MOV8817A

[J Q1E13MOV8817B-END-Page 8 of 8

FNP-1-FRP-S.1

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J't, RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Revision 25 Step 11 Action/Expected

Response ATTACHMENT

2 FAULTED SG ISOLATION Response NOT Obtained**************************************************************************************

CAUTION: A loss of secondary heat sink will result from failure to maintain at least one SG available for RCS cooldown.**************************************************************************************

1 Isolate all faulted SGs.1.1 Verify all faulted SG atmospheric

reliefs-MANUALLY CLOSED.Faulted SG 1A 1B 1C 1.1 Locally unlock and close one isolation valve for any failed atmospheric

relief.(127 ft, AUX BLDG main steam valve room)1A(lB,lC)MS ATMOS REL VLV PC[J 3371A[J 3371B[J 3371C Faulted SG Q1N11V 1A1B1C[J 004A[J 004C[J 004E[J 004B[J 004D[J 004F Key Z-131 Z-126 Z-125 Z-124 Z-123 Z-122 1.2 Verify all faulted SG main feed stop valves-CLOSED.Faulted SG 1A 1B 1C 1.2 Locally close all faulted SG main feed stop valves.(127 ft, AUX BLDG main steam valve room)MAIN FW TO 1A(lB,lC)SG STOP VLV Q1N21MOV[]3232A[]3232B[]3232C Step 1 continued on next page.___Page Completed Page 1 of 8

FNP-1-FRP-S.1

"..}...'1,..':::\\:i\.J::L..

J.t.RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Revision 25 Step 11 Action/Expected

Response ATTACHMENT

2 Response NOT Obtained 1.3 Verify blowdown from all faulted SGs-ISOLATED.1.3 Locally isolate blowdown.(121 ft, AUX BLDG rad side at PRIP)[J 7697A[J 7698A[J 7699A stopped stopped stopped[J 7697B[J 7698B[J 7699B stopped stopped stopped Faulted SG 1A(lB,lC)SGBD ISO Q1G24HV 1A[J 7614A closed 1B[J 7614B closed 1C[J 7614C closed Faulted SG 1A(lB,lC)SGBD PENE RM ISO Q1G24HV 1A 1B 1C**************************************************************************************

CAUTION: The TDAFWP will not be available if both steam supplies are isolated.At least one steam supply should remain aligned if TDAFWP required.**************************************************************************************

1.4 IF 1C SG faulted, THEN isolate TDAFWP steam supply from 1C SG.1.4.1 Isolate TDAFWP steam supply from 1C SG at hot shutdown panel.TDAFWP STM SUPP FROM 1C SG[J Q1N12HV3235B

in LOCAL (HSDP-F)TDAFWP STM SUPP FROM 1C SG[J Q1N12HV3235B

to STOP (HSDP-D)1.4 Proceed to step 1.5.1.4.1 Locally unlock and close STM LINE 1C TO TDAFWP ISO VLV Q1N12V005B.(Key Z-132)(127 ft, AUX BLDG main steam valve room)Step 1 continued on next page.___Page Completed Page 2 of 8

FNP-1-FRP-S.1

• t::}...Jiit..

J'I..RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Revision 25 Step 11 Action/Expected

Response ATTACHMENT

2 Response NOT Obtained 1.5 IF 1B SG faulted, THEN isolate TDAFWP steam supply from 1B SG.1.5.1 IF TDAFWP NOT required, THEN isolate TDAFWP steam supply from 1B SG at hot shutdown panel.TDAFWP STM SUPP FROM 1B SG[J Q1N12HV3235A/26

in LOCAL (HSDP-F)TDAFWP STM SUPP FROM 1B SG[J Q1N12HV3235A/26

to STOP (HSDP-D)1.5 Proceed to step 2.Step 1 continued on next page.___Page Completed Page 3 of 8

FNP-1-FRP-S.l....,....."..}..1..

..,i:::i..

jji...RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Revision 25 Step Il Action/Expected

Response ATTACHMENT

2 Response NOT Obtained**************************************************************************************

CAUTION: Failing open TDAFWP STM SUPP ISO Q1N12HV3226

will cause the RGSC to ramp to maximum output.Admitting steam to the TDAFWP with TDAFWP SPEED CONT SIC-3405 NOT set to 0%could cause a TDAFWP overspeed trip.**************************************************************************************

1.5.2 IF TDAFWP required, THEN perform one of the following.*Perform the following:

a)Close TDAFWP STM SUPP WARMUP ISO valves (BOP)[J Q1N12HV3234A

Closed[J Q1N12HV3234B

Closed b)IF the TDAFWP is NOT in operation, THEN adjust TDAFWP SPEED CONT to 0%[J SIC 3405 adjusted to 0%c)Open TDAFWP STM SUPP ISO QlN12HV3226

by failing air supply.(100 ft, AUX BLDG TDAFWP room)Step 1 continued on next page.___Page Completed Page 4 of 8

FNP-I-FRP-S.l

!::::...:.:....:)J..1.

ji*:....j..It.. RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Revision 25 Step II Action/Expected

Response ATTACHMENT

2 d)Isolate TDAFWP steam supply from IB SG at hot shutdown panel.TDAFWP STM SUPP FROM IB SG[J QIN12HV3235A/26

in LOCAL (HSDP-F)TDAFWP STM SUPP FROM IB SG[J QIN12HV3235A/26

to STOP (HSDP-D)e)Adjust TDAFWP SPEED CONT SIC 3405 as required when starting or stopping TDAFWP.*Locally unlock and close STM LINE IB TO TDAFWP ISO VLV QINI2V006A.(Key Z-13 0)(127ft, AUX BLDG main steam valve room)Response NOT Obtained___Page Completed Page 5 of 8

FNP-l-FRP-S.l

ii:""....,.,.....,..}..1.."'\,\::!J!:t..J:'l...Jl....RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Revision 25 Step 11 Action/Expected

Response ATTACHMENT

2 Response NOT Obtained 2 IF all SGs faulted, THEN maintain 20 gpm AFW flow to each SG.2.1 Control MDAFWP flow.MDAFWP FCV 3227 RESET[]A TRN reset[]B TRN reset MDAFWP TO lA/lB/lC SG B TRN[]FCV 3227 in MOD 2 Proceed to step 3.SG lA lB lC MDAFWP TO lA(lB,lC)SG QIN23HV[]3227A[]3227B[]3227C in MOD in MOD in MOD MDAFWP TO lA(lB,lC)SG FLOW CONT HIC[]3227AA[]3227BA[]322 7CA adjusted adjusted adjusted Step 2 continued on next page.___Page Completed Page 6 of 8

FNP-I-FRP-S.l

'\it:...:.:...::.J..1..*::\\"ii JiiL..J:\i.....!it RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Revision 25 Step 11 Action/Expected

Response ATTACHMENT

2 Response NOT Obtained 2.2 Control TDAFWP flow.TDAFWP FCV 3228[J RESET reset TDAFWP SPEED CONT[J SIC 3405 adjusted SG lA IB lC[]3228AA[]3228BA[]3228CA adjusted adjusted adjusted TDAFWP TO lA(lB,lC)SG QIN23HV[J3228A in MOD TDAFWP TO lA(IB,lC)SG FLOW CONT HIC[]3228B in MOD[J 3228C in MOD 2.3 Proceed to step 4.3 Isolate AFW flow to all faulted SGs.3.1 Close MDAFWP isolation valves to all faulted SGs.(BOP)3.1 Close MDAFWP flow control valves to all faulted SGs.Faulted SG lA IB lC Faulted SG lA IB lC MDAFWP TO MDAFWP TO lA (IB, lC)lA(IB,IC)SG SG ISO QIN23HV[J3227A[J 3227B[J 3227C QIN23MOV[J 37 64A[J 3764B[J 3764C in MOD in MOD in MOD[J 3764E[J 37 64D[J 3764F MDAFWP TO lA(IB,IC)SG FLOW CONT HIC[J 3227AA[J 322 7BA[J 3227 CA Step 3 continued on next page.___Page Completed Page 7 of 8

FNP-I-FRP-S.I

':[!:"" , ,/,[:..1..""\,::::::

J[:t J'[t...*L RESPONSE TO NUCLEAR POWER GENERATION/ATWT

Revision 25 Step 11 Action/Expected

Response ATTACHMENT

2 Response NOT Obtained 3.2 Close TDAFWP flow control valves to all faulted SGs.Faulted SG TDAFWP TO IA(IB,IC)SG QIN23HV IA[]3228A in MOD IB[]3228B in MOD IC[]3228C in MOD TDAFWP TO IA(IB,lC)SG FLOW CONT HIC[]3228AA[]3228BA[]3228CA 3.3 Locally unlock and close flow control valve inlet isolation to all faulted SGs.(100 ft, AUX BLDG above AFW pump rooms)Faulted SG IA IB IC QlN23V[]017A[]017B[J 017C Key Z-139 Z-170 Z-14I 4 Notify control room of SG isolation status.-END-Page 8 of 8

Farley Nuclear Plant 2006-301 SRO Inital Exam 90.076 G2.1.2 001 Given the following:

• Unit 2 is at 100%power with"A" Train on service.*At 1200 on 11/7/2007, 2E Service Water pump tripped and"B" Train SW was declared INOPERABLE.

Which ONE of the following describes the Technical Specification

REQUIRED ACTION lAW 3.7.8, Service Water System, and the action required to make"B" Train Service Water OPERABLE?A'!*Immediately

declare the DG supported by Train"B" Service Water INOPERABLE.

• Place"B" Train of SW on service and align 2C SW pump to auto start for 2E SW pump lAW SOP-24.0, Service Water System.B.*Immediately

declare the DG supported by Train"B" Service Water INOPERABLE.

• Align 2C SW pump to auto start for 2E SW pump lAW AOP-1 0.0, Loss of Service Water.c.*Declare the DG supported by Train"B" Service Water INOPERABLE

no later than 1600 on 11/7/2007 (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later).*Align 2C SW pump to auto start for 2E SW pump lAW AOP-10.0, Loss of Service Water.D.*Declare the DG supported by Train"B" Service Water INOPERABLE

no later than 1600 on 11/7/2007 (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> later).*Place B Train of SW on service and align 2C SW pump to auto start for 2E SW pump lAW SOP-24.0, Service Water System.Meets 10 CFR 55.43 (b)2 and 5 requirements

for SRO level question A.Correct.This TS immediately

entered from 3.7.8 and the DG is declared INOP.Then the 2C SW pump is aligned to auto start for 2E.The trains are swapped to do this.This will allow both trains to be operable.AOP-10 CAUTION: Based on plant needs,shiftingelectrical

trains in FNP-1-S0P-24.0, SERVICE WATER SYSTEMS, may be delayed.Subsequent

shifting of electrical

trains is required for train separation.

19 IF affected train NOT leaking, THEN evaluate aligning 1C SW pump to affected train using FNP-2-S0P-24.0, SERVICE WATER SYSTEM.Bases 3.7.8 Leo Two SWS trains are required to be OPERABLE to provide the required redundancy

to

Farley Nuclear Plant 2006-301 SRO Inital Exam ensure that the system functions to remove post accident heat loads, assuming that the worst case single active failure occurs coincident

with the loss of oftsite power.An SWS train is considered

OPERABLE during MODES 1, 2, 3, and 4 when: a.Two pumps are OPERABLE;and b.The associated

piping, valves, and instrumentation

and controls required to perform the safety related function are OPERABLE.Note from A.1 The first Note indicates that the applicable

Conditions

and Required Actions of LCO 3.8.1,"AC Sources-Operating," should be entered if an inoperable

SWS train results in an inoperable

emergency diesel generator.

FSD 181001 3.1.5.1 The Service Water pumps shall be automatically

started by a signal from the LOSP or ESS sequencer.

The Service Water swing pump shall be automatically

started by a signal from the LOSP or ESS sequencer when in service replacing one of the train oriented pumps.(References

6.7.039 and 6.1.009)SOP-24 P&L 3.3 Service Water pump lC may be selected for auto-start

from the ESS ortheLOSP sequencers, instead of an A Train or B Train pump, by using key-interlocked

selector switches at the SW local control panels.Normal position of both the A Train and B Train selector switches will be the lC position and lC SW pump will not autostart.

B.Incorrect.

This TS is immediately

entered from 3.7.8 and the DG is declared INOP.The second part is in part correct but B Train would be however AOP-1 0 sends the operator to SOP-24 to select the 2C SWP to autostart and if this was done wlo swapping trains it would be in an incorrect alignment.

This has to be done in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (3 days later)lAW TS 3.7.8.NOT 7 days.C.incorrect.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> would NOT be allowed to declare inop if DG was OOS.The second part is in NOT correct.See above.D.incorrect.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> would NOT be allowed to declare inop if DG was OOS.Second part of this is correct.

Farley Nuclear Plant 2006-301 SRO Inital Exam 076 Service Water System G2.1.2 Conduct of Operations:

Knowledge of operator responsibilities

during all modes of plant operation.

Question Number: 90 Tier 2 Group 1 Importance

Rating: 4.0 Technical Reference:

TS3.7.8,3.8.1, AOP-10, SOP-24 Proposed references

to be provided to applicants

during examination:

None Learning Objective:

10 CFR Part 55 Content: 43.2 Comments: fixed per FJE comments and added how to restore B train to operable status.

1/3/2008 14:27 FNP-2-AOP-I0.0

01-24-2005

Revision 15 FARLEY NUCLEAR

ABNORMAL OPERATING PROCEDURE FNP-2-AOP-I0.0

LOSS OF SERVICE WATER PROCEDURE USAGE REQUIREMENTS

SECTIONS CONTINUOUS

USE-Each step of the procedure is to be read prior to performing

that step.Each step is to be performed in the sequence given.Where required, each-step is to be signed off as complete before proceeding

to the next step.ALL S A F E T Y REFERENCE USE-The procedure is to be referred to periodically

to confirm that all required parts of a work activity have been performed.

Where required, steps are to be signed off to show that procedure requirements

have been met.R E L A T E D INFORMATION

USE-An activity may be performed from memory, but the procedure should be available for use as needed and for training.Approved: Ray Martin Operations

Manager 01/31/2005

Date Issued:_

..FNP-2-AOP-I0.0

LOSS OF SERVICE WATER Revision 15 Table of Contents Procedure Contains Number of Pages Body...................................

14 Attachment

1............................

1 Page 1 of 1

'FNP-2-AOP-I0.0

A.Purpose:::i:",,:::.:::

..::..:}...it..":::::::\,::1

.::1111....."::1:1:"..<;;;:*:::::::::, LOSS OF SERVICE WATER Revision 15 This procedure provides actions for response to a loss of one or both trains of service water.This procedure is applicable

at all times.B.Symptoms or Entry Conditions

I.This procedure is entered when a loss of either train of service water is indicated by any of the following:

a.Actuation of SW PRESS A TRN LO annunciator

AD4 or SW PRESS B TRN LO annunciator

ADS (60 psig)b.Actuation of SW PUMP TRIPPED annunciator

AE4 c.Actuation of SW TO AUX BLDG HDR PRESS A OR B TRN LO annunciator

AE5 (50 psig)d.Trip of any operating SW PUMP e.Rising temperatures

on components

supplied by service water f.Loss of power to one or both SW 4160 V busses 2K or 2L Page 1 of 14

FNP-2-AOP-I0.0

i?,'t::,t,:,:, r:: t:: iii*:,,:::.::.::.:::)

...It..*:\\:::1:

..Jij:*...JIlt.LOSS OF SERVICE WATER Revision 15 Step 11 Action/Expected

Response Response NOT Obtained NOTE: SW TO TURB BLDG ISO ACB)TRN valves will automatically

close if SW flow in either train is greater than 17,600 gpm.--I Verify affected SW 4160 V supply breakers closed.[]BKR DF02 closed[]BKR DG02 closed--2 IF a SW PUMP trips.THEN verify standby SW PUMP started.--3 IF SW pressure in both trains greater than 60 psig.THEN go to procedure and step in effect.**************************************************************************************

CAUTION: A running diesel generator will overheat if adequate SW flow is not provided.Steps 4.2.1 through 4.2.6 must be performed immediately

to verify adequate SW flow to a running diesel generator.

4 Check diesel generators.

4.1 Check any diesel generator in affected train-STARTED.4.1 Proceed to step 5.Step 4 continued on next page.___Page Completed Page 2 of 14

I/pr2uuo.i'-t.27 FNP-2-AOP-I0.0

';:;:::.::.:.:.:::::J.It.'\::\:

....:i:lt...if:lt.LOSS OF SERVICE WATER Revision 15 Step rJ Action/Expected

Response Response NOT Obtained NOTE: The loss of Service Water to the Turbine Building could be unisolable

and would affect both trains of Service Water.The intent of Step 4.2 RNO is to allow isolation of an affected train if possible.If both trains are affected then the Turbine Building must be isolated and the turbine generator removed from service.4.2 IF diesel generator NOT required, THEN secure diesel generator using ATTACHMENT

1.4.2 Perform the following SW isolations.

4.2.1 Isolate SW on the affected train(s)to the turbine building.Close A TRN SW TO TURB BLDG ISO valves.[]Q2P16V515[]Q2P16V516 (B trn elect)Close B TRN SW TO TURB BLDG ISO valves.[]Q2P16V514[]Q2P16V517 (A trn elect)Close A TRN SW FROM TURB BLDG HDR ISO valves.[]Q2P16V540[]Q2P16V542 VOL IAN Close B TRN SW FROM TURB BLDG HDR ISO valves.[]Q2P16V541[]Q2P16V543 Step 4 continued on next page.___Page Completed Page 3 of 14

FNP-2-AOP-I0.0

i::::': r":;::",:::,}:r.f:::::"".,.,"."../i...IL.*"\i\',.1.Jlt.....!IIt..<::;;:::::,f

LOSS OF SERVICE WATER Revision 15 Step 11 Action/Expected

Response Response NOT Obtained 4.2.2 IF both trains of service water have been isolated to the turbine building,.THEN perform the following:

4.2.2.1 IF Rx power is less than 35%, THEN trip the turbine and refer to FNP-2-AOP-3.0, TURBINE TRIP BELOW THE P9 SET POINT.4.2.2.2 IF Rx power is greater than 35%, THEN trip the reactor and refer to FNP-2-EEP-O.O, REACTOR TRIP 4.2.3 Perform FNP-2-AOP-7.0, LOSS OF TURBINE BUILDING SERVICE WATER in conjunction

with this procedure.

4.2.4 Close SW TO RCP MTR AIR CLRS Q2P16MOV313S

and SW TO BLDN HX&BTRS CHLR Q2P16MOV3149.

4.2.S Verify diesel bUilding SW header valves open.SW TO/FROM DG BLDG HDR A[]Q2P16V519/S37

open SW TO/FROM DG BLDG HDR B[]Q2P16V518/S36

open Step 4 continued on next page.___Page Completed Page 4 of 14

'FNP-2-AOP-10.0:II',: ('\"'":'",;:':I}i:::I\".""..".i J..Jt..*"'t:\Ii..Jilt......:-1:1\..

,,:::;:;:::::':,:,::

LOSS OF SERVICE WATER Revision 15 Step 11 Action/Expected

Response Response NOT Obtained 4.2.6 IF unable to maintain running diesel generator(s)

lube oil temperature

below the alarm(155'

DG BLDG local control panel)THEN perform the following.

4.2.6.1 For shared diesel generators

verify Unit 1 Service Water aligned.NOTE: 5 No evaluation

has been performed to demonstrate

that the Unit 1'B'Train Service Water System is capable of supplying the cooling requirements

for IB and 2B diesel at the same time.4.2.6.2 IF Unit 1 SW is available for 2B diesel generator,.THEN align Unit 1 SW supply to 2B diesel generators.

2B DIESEL GENERATOR SW SUPP TO/FROM UNIT 1 (UNIT 2)[]QIP16V592/s93

open[]Q2P16V592/s93

closed 4.2.7 IF unable to maintain running diesel generator(s)

lube oil temperature

alarm clear (155'DG BLDG local control panel)THEN stop affected diesel generator.using

ATTACHMENT

1.Verify all available SW PUMPs STARTED.___Page Completed Page 5 of 14

FNP-2-AOP-I0.0

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.,.,1:1::'.

....111...,;':;::;::;::",,/

LOSS OF SERVICE WATER Revision 15 Step 11 6 Action/Expected

Response Check pressure in a SW train GREATER THAN 60 psig.6 Response NOT Obtained IF, one train of Service Water cannot be immediately

restored to the Turbine Building,.THEN.perform

the following:

6.1 Isolate SW to the turbine bUilding.Close SW TO TURB BLDG ISO A TRN ISO valves.[]Q2P16V515[]Q2P16V516 (B Trn Electrical)

Close SW TO TURB BLDG ISO A TRN ISO valves.[]Q2P16V514[]Q2P16V517 (A Trn Electrical)

Close SW FROM TURB BLDG A HDR ISO valves[]Q2P16V540[]Q2P16V542 Close SW FROM TURB BLDG B HDR ISO valves[]Q2P16V541[]Q2P16V543 6.2 IF Rx power is less than 35%, THEN trip the turbine and refer to FNP-2-AOP-3.0, TURBINE TRIP BELOW THE P9 SET POINT.6.3 IF Rx power is greater than 35%,.THEN trip the reactor and refer to FNP-2-EEP-O.O, REACTOR TRIP 6.4 Close SW TO RCP MTR AIR CLRS Q2P16MOV3135

and SW TO BLDN HX&BTRS CHLR Q2P16MOV3149.

6.5 Perform FNP-2-AOP-7.0, LOSS OF TURBINE BUILDING SERVICE WATER in conjunction

with this proceaure.

Step 6 continued on next page.___Page Completed Page 6 of 14

FNP-2-AOP-I0.0

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..:1:""::::::::::'1

..J!l:l...Jil:...:::::::;;::::.:::{

LOSS OF SERVICE WATER Revision 15 Step 11 Action/Expected

Response Response NOT Obtained 6.6 Verify SW isolated to standby CCW heat exchanger.

Standby CCW HX SW TO 2C(2B,2A)CCW HX Q2P16MOV 2C[]3130C closed 2B[]3130B closed 2A[]3130A closed 6.7 Maintain SW flow to in service CCW heat exchanger 3500-4000 gpm.In Service CCW HX 2C 2B 2A 2C(2B,2A)CCW HX DISCH FCV HIC[]3009C[]3009B[]3009A adjustedadjustedadjusted

7 8 9 Check operating CCW trainSUPPLIED FROM AFFECTED SW TRAIN.Verify CCW PUMP in non affected train-STARTED.Verify CRG PUMP in non affected train-STARTED.7 Proceed to step 14.**************************************************************************************

CAUTION: Steps 8 and 9 must be complete before step 10 is performed to ensure seal injection is maintained

to the RCPs.**************************************************************************************

_10_11 Verify all CRG PUMPs in affected train-STOPPED.Perform FNP-2-AOP-9.0, LOSS OF 1M..., IN K RJ ('()()T Tun Wf...rrER in conjunction

with this procedure.

___Page Completed Page 7 of 14

'FNP-2-AOP-I0.0

-;::::c r

JI*I*:..Jiiit.::(;:.:*::::;:/

LOSS OF SERVICE WATER Revision 15 12.1 IF reactor critical, THEN perform the following.

Step Il 12 Action/Expected

Response Monitor Rep motor bearing temperatures

-LESS THAN 195°F.12 Response NOT Obtained Perform the following.

NOTE: The remainder of this procedure should be performed in conjunction

with FNP-2-ESP-O.l, REACTOR TRIP RESPONSE if sufficient

personnel are available.

12.1.1 Trip the reactor.12.1.2 IF reactor tripped, THEN stop all RCPs.RCP[]2A[]2B[]2C 12.1.3 Proceed to step 13.12.2 IF reactor NOT critical, THEN perform the following.

12.2.1 Verify all reactor trip and reactor trip bypass breakers open.[]Reactor trip breaker A[]Reactor trip breaker B[]Reactor trip bypass breaker A[]Reactor trip bypass breaker B 12.2.2 Stop all RCPs.RCP[]2A[]2B[]2C 12.2.3 IF unit in Mode 3 or 4,

perIorm l:!-Nt'LAUP 7I.0, LOSS OF REACTOR COOLANT FLOW in conjunction

with this procedure.

___Page Completed Page 8 of 14

IP/LVVtD l"t.LI FNP-2-AOP-I0.0

'\:::.:::,,,:,,:::.JL**:tt::::.:.:ll::::.

..j::.t.;:;:(,:.:::::::/

LOSS OF SERVICE WATER Revision 15 Step 11_13 Action/Expected

Response Minimize CCW loads in affected train.Response NOT Obtained 13.1 Check on service SFP HXSUPPLIED FROM NON AFFECTED SW TRAIN.13.2 IF RHR system in operation, THEN check operating RHR train supplied from non affected SW train.13.1 Place non affected SFP HX in service using FNP-2-S0P-S4.0, SPENT FUEL PIT COOLING AND PURIFICATION

SYSTEM.13.2 IF RHR system in operation, THEN perform the following.

13.2.1 Place non affected RHR train in service using FNP-2-S0P-7.0, RESIDUAL HEAT REMOVAL SYSTEM.13.2.2 Secure affected RHR train using FNP-2-S0P-7.0, RESIDUAL HEAT REMOVAL SYSTEM.NOTE: The CCW Pump Room Coolers are not considered

to be attendant equipment;

however, the room cooler fan must be tagged out of service when SW is lost to the affected cooler(s)(Ref.NEL-96-0101;

REA 95-0873).13.3 Check on service CCW trainSUPPLIED FROM NON AFFECTED SW TRAIN.___Page Completed Page 9 of 14 13.3 Align non affected CCW train as on service train using FNP-2-S0P-23.0, COMPONENT COOLING WATER SYSTEM.

FNP-2-AOP-I0.0

LOSS OF SERVICE WATER Revision 15 Step 11 Action/Expected

Response Response NOT Obtained 14 Minimize SW loads in affected train.14.1 If required, secure BTRS using FNP-2-S0P-3.0, BORON THERMAL REGENERATION

SYSTEM.14.2 Minimize A TRAIN SW LOADS as required.14.2.1 Secure SGBD using FNP-2-S0P-16.1, STEAM GENERATOR BLOWDOWN PROCESSING

SYSTEM.14.2.2 Close SW TO BLDN HX&BTRS CHLR Q2P16MOV3149

14.2.3 Stop A TRAIN CTMT CLRS[]A Ctmt Cooler Q2EI2HOOIA-A

[]B Ctmt Cooler Q2EI2HOOIB-A

14.3 Minimize B TRAIN SW LOADS as required.14.3.1 Close SW TO RCP MTR AIR CLRS Q2P16MOV3135.

14.3.2 Stop B TRAIN CTMT CLRS[]C Ctmt Cooler Q2EI2HOOIC-B

[]D Ctmt Cooler Q2EI2HOOID-B

14.4 Verify CTMT CLRS in non-affected

train-STARTED.A TRAIN CTMT CLRS[]A Ctmt Cooler Q2EI2HOOIA-A

[]B Ctmt Cooler Q2EI2HOOIB-A

B TRAIN CTMT CLRS[]C Ctmt Cooler Q2EI2HOOIC-B

[]D Ctmt Cooler Q2EI2HOOID-B

15 Evaluate event classification

and notification

requirements

___Page Completed Page 10 of 14

,...__I/.JI LUVO 1"t.L IFNP-2-AOP-10.0:::..:::::::::::.::.:):.Jt..::::::::\:!

...'1':1....Jl...:::::;;;;:;:;:::/

LOSS OF SERVICE WATER Revision 15 Step Il_16 Action/Expected

Response Check pressure in both SW trains-GREATER THAN 60 psig.16 Response NOT Obtained Perform the following.

16.1 Verify affected train SW PUMP MINI FLOW valves closed.(SWIS)16.2 Dispatch personnel to inspect SW system for leakage.16.3 WHEN SW system leakage source is identified, THEN isolate leakage.16.4 Close affected train dilution bypass line isolation valve.Affected train DILUTION BYPASS ISOLATION VALVE Q2P16V A[]558 155 AUX bldg RADSIDE HALL B[]557 155 AUX bldg RADSIDE HALL_17 Go to procedure and step in effect.16.5 IF pressure in both SW trains greater than 60 psig, THEN go to procedure and step in effect IF NOT, proceed to step 18.___Page Completed Page 11 of 14

-- 1.....L.I t FNP-2-AOP-I0.0 1!:[\,:".".,.,}.Jt.*"'t::::;1.j!:ll.......l!:!t...,,(;;:.::::,,{, LOSS OF SERVICE WATER Revision IS Step Action/Expected

Response 11 III--18 Verify SW alignment to diesel generators

based on affected train: 18.1 IF affected train has a Shared diesel generator running THEN verify Unit 1 SW aligned.1-2A DIESEL GENERATOR (A TRN)SW SUPP TO/FROM UNIT 1 (UNIT 2)[]QIPI6VS26/S34

open[]QIPI6VS27/S3S

closed lC DIESEL GENERATOR (A TRN)SW SUPP TO/FROM UNIT I(UNIT 2)[]QIPI6VS24/S32

open[]QIPI6VS2S/S33

closed 2C DIESEL GENERATOR (B TRN)SW SUPP TO/FROM UNIT I(UNIT 2)[]QIPI6VS21/S29

open[]QIPI6VS20/S28

closed Response NOT Obtained NOTE: No evaluation

has been performed to demonstrate

that the Unit 1'B'Train Service Water System is capable of supplying the cooling requirements

for IB and 2B diesel at the same time.18.2 IF Unit 1 SW is available for 2B diesel generator,.THEN align Unit 1 SW supply to 2B diesel generators.

2B DIESEL GENERATOR SW SUPP TO/FROM UNIT I(UNIT 2)[]QIPI6VS92/S93

open[]Q2P16VS92/S93

closed___Page Completed Page 12 of 14

• • FNP-2-AOP-10.0 m if:\\:.:l m:).:r:::[\::::.:::,.::

..1..Jt.*:\:\!\:

.Jilt..J!:!:'..:::::;::.:::::/

LOSS OF SERVICE WATER Revision 15 Step 11 Action/Expected

Response Response NOT Obtained**************************************************************************************

CAUTION: To prevent a leak on one train from affecting both trains, 2C SW pump must not be realigned to a train with an unisolated

leak.**************************************************************************************

CAUTION: Based on plant needs, shifting electrical

trains in FNP-I-S0P-24.0, SERVICE WATER SYSTEMS, may be delayed.Subsequent

shifting of electrical

trains is required for train separation.

___19 IF affected train NOT leaking.THEN evaluate aligning lC SW pump to affected train using FNP-2-S0P-24.0.

SERVICE WATER SYSTEM.___20 Align 2C battery charger room cooler to non affected train using FNP-2-S0P-37.1.

125 V D.C.AUXILIARY BUILDING DISTRIBUTION

SYSTEM.___21 Align 2B charging pump to non affected train using FNP-2-S0P-2.1.

CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION.

___22 Monitor 600 V load centers cooled by affected train.22.1 IF load center operation is degraded, THEN evaluate transferring

loads to a non affected load center using FNP-2-S0P-36.3, 600, 480 AND 208/120 VOLT AC ELECTRICAL

DISTRIBUTION

SYSTEM._23 Check pressure in both SW trains-GREATER THAN 60 psig.23 Return to step 1.___Page Completed Page 13 of 14

It:="'r;1'"1'.27 I" I 1 ,iNP-2-AOP-10.0

..Jt.'::'\\':.,":.:'1...

.Jilt..::,:::::::;::::::::::, LOSS OF SERVICE WATER Revision 15 Step 11 Action/Expected

Response ATTACHMENT

1 Response NOT Obtained 1 SECURING A DIESEL GENERATOR Secure affected diesel generator from EPB.1.1 Place the affected diesel generator MODE SELECTOR SWITCH to MODE 2.1.2 Depress affected diesel generator DIESEL EMERG START RESET pushbutton.

CAUTION: Failure to perform steps 1.4 and 1.5 immediately

following step 1.3 may result in restart of the diesel generator when the low speed relay de-energizes.

1.3 Depress affected diesel generator STOP pushbutton.

[]DIESEL STOP light lit 1.4 Place affected diesel generator MODE SELECTOR SWITCH to MODE 3.1.5 Depress affected diesel generator DIESEL EMERG START RESET pushbutton.

1 Secure affected diesel generator from diesel local control panelft, DIESEL BLDG).a)Place affected diesel generator MODE 4 SELECTOR SWITCH to MODE 4 b)Depress affected diesel generator local STOP pushbutton.-END-Page 1 of 1

06/27/07 09:13:27 FNP-2-S0P-24.0

4.5 Aligning Train B (A)SW to charging pump 2B room cooler.NOTE: Service water to charging pump 2B room cooler shall be aligned to the same train that charging pump 2B is aligned to in the CVCS.This procedure should be performed by FNP-2-S0P-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION, which aligns charging pump 2B to Train B (A).4.5.1 Align Train B (A)SW to Charging Pump 2B Room Cooler per FNP-2-S0P-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION.

4.6 Aligning service water pump 2C to A train.4.6.1 To align service water pump 2C to A train, perform FNP-2-S0P-24.0C.

4.7 Aligning service water pump 2C to B train.4.7.1 To align service water pump 2C to B train, perform FNP-2-S0P-24.0D.

4.8 Shutdown of service water system train A (B).NOTE: Prior to taking any actions that will significantly

affect service water dilution flow, notify the shift radiochemist

to ensure any chlorination

can be adjusted or terminated

as needed.4.8.1 Close SW FROM TURB BLDG A (B)HDR ISO valves:*Q2P16V540

• Q2P16V542 (Q2P16V543).

4.8.2 Close SW TO TURB BLDG A (B)TRN*Q2P16V515 (Q2P16V514)

• Q2P16V516 (Q2P16V517).

4.8.3 Secure all but one A(B)train service water pump.10 Version 51.0

06/27/07 09:13:27 FNP-2-S0P-24.0D

SYSTEM CHECKLIST SYSTEM CHECKLIST SOP-24.0D ALIGNING SW PUMP 2C TO B TRAIN Situation Requiring Completion

Of Check List: Performed By:_Verified By: Reviewed By: Date/Time Date/Time Date/Time_This Check List consists of 6 pages.Version 51.0

06/27/0709:13:27

FNP-2-S0P-24.0D

SYSTEM CHECKLIST SYSTEM CHECKLIST SOP-24.0D ALIGNING SW PUMP 2C TO B TRAIN 1.0 Electrical

Alignment 1.1 1.2 1.3 1.4 1.5_/_1.6 CV NOTE: 1.7 1.8 1.9 1.10 The version of this procedure has been verified to be the current version for the task.(OR 1-98-498)The version of this procedure has been verified to be for the correct unit for the task.(OR 1-98-498)IF 2C service water pump is to be aligned for auto-start, THEN obtain key#LL299 from the Shift Support Supervisor.

Stop or verify stopped 2C service water pump.IF 2C service water pump is selected to Auto Start on A Train, THEN select 2C position on A Train spare pump selector switch and remove key#LL299.Open DC control power breaker for DK05-2, SERVICE WATER PUMP 2C Q2P16M001C-AB.

During the performance

of the following steps of racking out the breaker and removing it from the cubicle, special consideration

should be given to prevent damage to the key or to the interlock.(OR 1-98-009)Rack out circuit breaker DK05-2, SERVICE WATER PUMP 2C Q2P16M001C-AB, to the DISC (disconnect)

position.Tum key#RE-11579 in the mechanical

interlock on the circuit breaker DK05-2, SERVICE WATER PUMP 2C Q2P16M001C-AB, and remove the key.IF required for seismic consideration, THEN remove circuit breaker DK05-2, SERVICE WATER PUMP 2C Q2P16M001C-AB, from the cubicle and take appropriate

actions with the breaker.Insert key#RE-11579 into mechanical

interlock on SERVICE WATER pIIMP 2C 4KV DISC SW 2A, Q2R18A501A-A, and tum key.Key#RE-11579 is now held in place.Page 1 of 6 Version 51.0

06/27/07 09:13:27 FNP-2-S0P-24.0D

SYSTEM CHECKLIST_/_1.11 CV 1.12 1.13_/_1.14 CV 1.15 NOTE: 1.16 1.17 1.18_/_1.19 CV Open SERVICE WATER PUMP 2C 4KV DISC SW 2A, Q2R18A501A-A

and verify the position indicator reads SW OPEN.Turn key#RE-11578 in its mechanical

interlock on SERVICE WATER PUMP 2C 4KV DISC SW 2A, Q2R18A501A-A

and remove key.Disconnect

2A is now locked open.Insert key#RE-11578 into its mechanical

interlock on SERVICE WATER PUMP 2C 4KV DISC SW 2B, Q2R18A501B-B, and turn key.Key#RE-11578 is now held in place.Close SERVICE WATER PUMP 2C 4KV DISC SW 2B, Q2R18A501B-B

and verify thepositionindicator

reads SW CLOSED.Tum key#RE-11580 in its mechanical

interlock on SERVICE WATER PUMP 2C 4KV DISC SW 2B, Q2R18A501B-B, and remove key.Disconnect

switch 2B is now locked closed.During the performance

of the following steps of returning the breaker to the cubicle and racking it in, special consideration

should be given to prevent damage to the key or to the interlock.(OR 1-98-008)Rack or verify racked circuit breaker DL05-2, SERVICE WATER PUMP 2C Q2P16M001C-AB

to the DISC (disconnect)

position.Insert key#RE-14253 into the mechanical

interlock on circuit breaker DL05-2, SERVICE WATER PUMP 2C Q2P16M001C-AB, and turn key.Key#RE-14253 is now held in place.Rack circuit breaker DL05-2, SERVICE WATER PUMP 2C Q2P16M001C-AB

to the connected position.Close DC control power breaker for DL05-2, SERVICE WATER PUMP 2C Q2P16M001C-AB

and verify breaker spring charges.Page 2 of6 Version 51.0

06/27/07 09:13:27 2.0 Mechanical

Alignment FNP-2-S0P-24.0D

SYSTEM CHECKLIST 2.1 On Service Water Pumps cooling header close or verify closed the following valves: 2.1.1 A trn S.W.pump motor clg water header iso valve Q2P16V712 2.1.2 A trn S.W.pump motor clg water header iso valve Q2P16V713 2.2 Open or verify open the following valves: 2.2.1 B trn S.W.pump motor clg water header iso valve Q2P16V714 2.2.2 B trn S.W.pump motor clg water header iso valve Q2P16V715 NOTE: IF 2C Service Water Pump is already aligned to B Train, THEN step 2.3.1 and 2.3.2 may be marked Nt A.2.3 At the SW structure, close the following breakers (in any order): 2.3.1 FK-L2 SW pmp 2C to SW HDR A Q2P16V507.

2.3.2 FL-L2 SW pmp 2C to SW HDR B Q2P16V506.

NOTE: Service water pump 2C train A and B header isolation valves Q2P16V506 and Q2P16V507 should not be open or stroking simultaneously

to prevent cross connection

of trains.2.4 On the main control board close or verify closed 2C SW PUMP TO A HDR ISO Q2P16V507.

2.5 On the main control board open or verify open 2C SW PUMP TO B HDR ISO Q2P16V506.

2.6 At the SW structure, open the following breakers (in any order): 2.6.1 FL-L2 SW pmp 2C to SW HDR B Q2P16V506.

2.6.2 FK-L2 SW pmp 2C to SW HDR A Q2P16V507.

Page 3 of6 Version 51.0

06/27/07 09:13:27 FNP-2-S0P-24.0D

SYSTEM CHECKLIST 2.7 INDEPENDENTL

Y VERIFY the following at the SW structure:

2.7.1 A trn S.W.pump motor clg water header iso valve Q2P16V712 closed.IV 2.7.2 A trn S.W.pump motor clg water header iso valve Q2P16V713 closed.IV 2.7.3 B trn S.W.pump motor clg water header iso valve Q2P16V714 open.IV 2.7.4 B trn S.W.pump motor clg water header iso valve Q2P16V715 open.IV 2.7.5 Breaker FL-L2 for SW pmp 2C to SW hdr B Q2P16V506 open.IV 2.7.6 Breaker FK-L2 for SW pmp 2C to SW hdr A Q2P16V507 open.IV 2.8 INDEPENDENTLY

VERIFY the followi,ng

on the MCB (verification

may be performed locally if desired).2.8.1 2C SW PUMP TO A HDR ISO Q2P16V507 closed.IV 2.8.2 2C SW PUMP TO B HDR ISO Q2P16V506 open.IV NOTE: 2.9 The next step preferred action is to start the 2C SW pump and place it on-service.

If extenuating

circumstances

preclude placing the pump on-service, then bumping the pump is allowed with the shift supervisor's

permission.

Perform one of the following:

2.9.1 IF desired, THEN place the 2C service water pump on-service

..2.9.2 IF desired, THEN bump service water pump 2C 2.10 IF NOT needed in section 3.0, THEN return key#LL299 to the Shift Support Supervisor.

Page 4 of 6 Version 51.0

06/27/07 09:13:27 FNP-2-S0P-24.0D

SYSTEM CHECKLIST 3.0 Selecting 2C SW pump for B Train auto-start

NOTES:*The following steps may be performed even if 2C SW pump is already running.*IF 2C SW pump is running on B trn as indicated by a red running light on DLOS handswitch, THEN only section 2.0 of the alignment need be completed.

• IF 2C SW pump is selected for auto-start

in B Train, THEN the 2D or the 2E SW pump it replaces will NOT sequence on following an SI or LOSP.3.1 Verify that 2C SW pump is aligned mechanically

and electrically

to B Train per the above sections 1.0 and 2.0.NOTE: The following step is performed to ensure that the 2C SW Pump will start and run normally prior to selecting it for autos tart.(OR 2-98-070)IF the 2C SW Pump is already running, THEN step 3.2 may be marked Nt A.3.2 Bump the 2C Service Water Pump to verify that it will start and run normally.3.3 IF NOT obtained in section 1.0, THEN obtain Key#LL299 from the Shift Support Supervisor.

3.4 Check that the 2C SW pump A Train auto-start

selector switch is in the 2C position.IF NOT, THEN stop and notify the Shift Supervisor.

NOTE: Key may only be inserted or removed if switch is in the 2C position.3.5 Insert Key#LL299 into the 2C SW pump B Train spare pump selector switch lock.(Directly above spare pump selector switch.)3.6 Turn Key#LL299 clockwise.

The key is now held in place.Select 2D or 2E pump wIth the spare pump selector sWItch.Record posItion selected.________Position Page 5 of6 Version 51.0

06/27/07 09: 13:27 FNP-2-S0P-24.0D

SYSTEM CHECKLIST 3.7 INDEPENDENTLY

VERIFY 2C SW pump B Train spare pump selector switch selected to 2D or 2E pump with Key#LL299 held in place.3.8 Place a caution tag on the MCB B Train handswitch

for SW pump 2C noting the auto-start

selector switch position.4.0 Returning 2C Service Water pump auto-start

to normal.NOTE: Steps 4.1 and 4.2 are performed to ensure that the de-selected

B Train SW Pump will start and run normally prior to selecting it for autostart.(OR 2-98-070)IF the de-selected

B Train SW Pump is already running, THEN steps 4.1 and 4.2 may be marked Nt A.4.1 Verify that the pump recorded in step 3.6 of this checklist is aligned per System Checklist FNP-2-S0P-24.0A.

4.2 Bump the B Train pump identified

in step 4.1 of this checklist to verify that it will start and run normally.4.3 Select 2C with the spare pump selector switch.4.4 Tum key#LL299 counterclockwise

and remove key.4.5 Return key#LL299 to the Shift Support Supervisor.

4.6 Remove the caution tag from the MCB BTrainhandswitch

for 2C SW Pump.4.7 INDEPENDENTLY

VERIFY 2C SW pump B Train spare pump selector switch selected to 2C SW pump.4.8 INDEPENDENTLY

VERIFY2C SW pump B Train spare pump selector switch Key#LL299 removed.Page 6 of6 Version 51.0

09/28/07 14:02:43 FNP-2-ARP-I.I

LOCATION AE4 SETPOINT: 1.Not Applicable

ORIGIN: 52-B Contact on anyone of the following breakers 1.DK03-2A SW Pump 2.DK04-2B SW Pump 3.DK05-2C SW Pump A Train 4.DL05-2C SW Pump B Train 5.DL03-2D SW Pump 6.DL04-2E SW Pump PROBABLE CAUSE SW PUMP TRIPPED 1.2A, 2B, 2C, 2D, or 2E Service Water Pump tripped due to an overload or an electrical

fault.AUTOMATIC ACTION NONE OPERATOR ACTION , J,..':).I/'-;VL--&>k.at1 Ch k*d**dd.r7.h*h*

.ec In lcatlons an

serVIce water pump as trlppe.*2.Start another service water pump[n the same traimas the tripped pump.3.Refer to FNP-2-AOP-IO.0, LOSS OF SERVICE WATER.4.Refer to Technical Specification

3.7.8 for LCO requirements

with a loss of train A or B service water.5.Notify appropriate

personnel to determine and correct the cause of the alarm.6.Return the Service Water electrical

and component lineup to normal as soon as possible.References:

A-207IOO, She 74A-C;D-202747;D-202748;

D-202749;D-202750;D-20275I;D-202752;Technical Specification

3.7.8 Page 1 of 1 Version 27.0

Farley Nuclear Plant 2006-301 SRO Inital Exam 1 00.G2.4.44 045 A Site Area Emergency was declared 35 minutes ago.Subsequently, conditions

have degraded and a General Emergency classification

needs to be declared.When upgrading to the General Emergency classification, which one of the following contains ONLY required actions lAW FNP-0-EIP-9.0, Emergency Actions?A.*Sounding of the plant emergency alarm.*Announce needed evacuation

instructions

to plant personnel.*Sounding of the plant emergency alarm.*Notify Alabama and Georgia of the status of the unaffected

Unit.C.*Notify Alabama and Georgia of Protective

Action Recommendations.

• Announce needed evacuation

instructions

to plant personnel.

D.*Notify Alabama and Georgia of Protective

Action Recommendations.

• Notify Alabama and Georgia of the status of the unaffected

Unit.Meets 10 CFR 55.43 (b)requirements

for SRO level question since the IR is a 2.1 for an RO and not required knowledge or an action for an RO.EIP-9.0 A: Incorrect:

This action is required by the General Emergency Guideline Procedure only when not already previously

performed.

The SRO must know that it was required, and was already sounded, for the SAE.Second part correct II.Emergency Director Actions NOTE: THE SHIFT MANAGER SHALL PERFORM THE DUTIES OF THE EMERGENCY DIRECTOR UNTIL HIS ARRIVAL AND ASSUMPTION

OF DUTIES.Initials A.Notify personnel on site 1.If the Plant Emergency alarm has not already been activated, then announce over the public address system"All Plant Personnel Report to Designated

Assembly Area," activate the PEA[Plant Emergency alarm]for 30 seconds and repeat the announcement.

2.Announce the classification, and the condition, request setup of the TSC and OSC and give needed evacuation

instructions

over plant public address system.

Farley Nuclear Plant 2006-301 SRO Inital Examloner!I 19 f9 E I!I J!t

Jllli'iM:jB$li:_Wi

_B.Correct: Notification

of Protective

Action Recommendations

is required to be completed for the Initial Notification

of a General Emergency.(Not required for any other classification

including Site Area Emergency).

Announcement

with evacuation

instructions

required per step II.A.2.of Guideline 2, EIP-9.0.C: Incorrect:

First part correct, second part incorrect.

For initial notifications

the Form"Guideline

1" states: (Unaffected

Unit(s)Status Not Required for Initial Notifications)

D: Incorrect:

First part correct, second part incorrect.

G2.4,44 Knowledge of emergency plan protective

action recommendations.

Question Number: 100 Tier 3 Group 4 Importance

Rating: 4.0 Technical Reference:

EIP-9.0 Proposed references

to be provided to applicants

during examination:

NO Learning Objective:

10 CFR Part 55 Content: 43.5 Comments: Replaced the question with one that does not require reference matenal and IS not a direct lookup.It is more closely related to what an SRO duty is in the emergency plan and required knowledge for an SRO.

09/28/07 13:10:44 GUIDELINE 1 GENERAL EMERGENCY FNP-O-EIP-9.0

GUIDELINE 1 I.Purpose of Classification

The classification

of General Emergency applies to those events which are in progress or have occurred which involve actual or imminent substantial

core degradation

or melting with potential loss of containment

integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.The potential for release of radioactive

material for the General Emergency classification

is more than 1000 Ci of 1-131 equivalent

or more than 10 6 Ci ofXe-133 equivalent.

The purpose of the declaration

of a General Emergency is to: (a)Initiate predetermined

protective

actions for the public.(b)Provide continuous

assessment

of information

from licensee and offsite measurement.(c)Initiate additional

measures as indicated by event releases or potential releases and, (d)Provide current information

for and consultation

with offsite authorities

and the public.A General Emergency would be declaredbasedon FNP-O-EIP-9.2

II.Emergency Director Actions NOTE: THE SHIFT MANAGER SHALL PERFORM THE DUTIES OF THE EMERGENCY DIRECTOR UNTIL IDS ARRIVAL AND ASSUMPTION

OF DUTIES.Initials A.1.2.Notify personnel on site@he Plant Emergency alarm ha@lready been activated, then announce over the public address system"All Plant Personnel Report to Designated

Assembly Area,"

the PEA for 30 secondsandrepeatthe

announcement;.

...1

[;JJIApe-A q r A.c.U 4 t-e..ee{:.-crJ"R E Announce the classification,andthe conoition, request setup of the TSC and OSC and give needed evacuation

instructions

over plant public address system.Page lof8 Version 59.0

09/28/07 13:10:44

GUIDELINE 1 GENERAL EMERGENCY FNP-0-EIP-9.0

GUIDELINE 1 B.Callout the ERO staff 1.Activate the ERO callout system per FNP-0-EIP-8.3, Table 2.(Located in the Unit 2 SS desk)NOTE: IF POSSIBLE AND TIME PERMITTING, DISCUSS WITH ALABAMA RADIATION CONTROL AND GEORGIA EMERGENCY MANAGEMENT

AGENCY ABOUT THE PARs PRIOR TO ANNOUNCING

THEM OVER THE ENN.C Complete Notification

form 1.Fill in the General Emergency Initial Notification

Form (last pages of this guideline), including developing

protective

action recommendations

per step L.Take into account the zones and evacuation

time estimates shown in Figure 1.NOTE: INITIAL NOTIFICATIONS

WILL NORMALLY BE MADE BY THE OPERATIONS

SHIFT COMMUNICATOR, BUT MAY BE MADE BY OPERATIONS

STAFF, TSC STAFF OR OTHER QUALIFIED PERSON USING THE INITIAL NOTIFICATION

FORM (LAST PAGES OF THIS GUIDELINE).

NOTE: INITIAL AND UPGRADE CLASSIFICATIONS

AND NOTIFICATIONS

SHOULD BE PERFORMED BY THE CONTROL ROOM OR THE TSC STAFF, WITH THE EOF INFORMED AS SOON AS POSSIBLE.D.Initial Notifications

___1.Within 15 minutes of declaration, verbally notify the state and local agencies using the General Emergency Initial Notification

Form (last pages of this guideline)

.___2.Verify notifications

complete and documented

on the General Emergency Initial Notification

Form (last pages of this guideline).

___3.Complete Figure 6, follow-up message.Instructions

for completing

the form are available as part of the figure.___4.Within one hour of the General Emergency Initial Notification

Form (Verbal Notification)

transmittal, fax Figure 6, follow-up message to state and local agencies.The goal should be within 30 minutes of the verbal notification.

5.Complete Figure 5, NRC notification

message.Instructions

for completing

the form are available in Figure 5.Page 2 of8 Version 59.0

09/28/07 13:10:44"H'W--".GUIDELINE 1 GENERAL EMERGENCY FNP-0-EIP-9.0

GUIDELINE 1___6.Provide the information

on Figure 5, to the NRC as soon as possible, but within one hour of the declaration

per the instructions

on Figure 5.E.Emergency Organization

Notifications

1.On-call Emergency Director 2.On-call EOF Manager 3.SNC Duty Manager 4.Notify Security of Emergency, incoming personnel and access restrictions

(4611).F.Other Notifications

1.Have Regulatory

ERDS activated to transmit data to the NRC within one hour of the declaration

of the emergency (EIP-8-3, step 10).2.Ifpersonnel

injury or fire is involved, refer to FNP-0-EIP-l1.0

and 13.0 respectively

for additional

actions and EIP-8.0 steps 5.0 and 6.0 for additional

notification

requirements.

3.U.S.Army EOD group at Fort Benning, GA, ifnecessary.

4.Savannah River Operations

Office, ifnecessary.

5.If there is a security event involved ensure appropriate

notifications

and actions of FNP-0-AOP-49

and FNP-O-SP 37.0 are performed 6.If there is a security event involved and access to the plant from off site is restricted

by local law enforcement (LLE)and it is desired to bring a plant employee to the site or additional

off site resources such as fire departments

or law enforcement

then perform the following:

• Contact the Houston County EMA to arrange a route and provide the names of individuals

or resources that require access to the plant for relay to LLE.*In conjunction

with Houston County EMA determine on site and off site staging areas for off-site resources using Appendix 1*Inform the individuals

and resources that are coming to the site of the required route to the site.Individuals

must have a company picture ID to get through the roadblocks

Page 3 of8 Version 59.0

09/28/07 13:10:44 FNP-0-EIP-9.0

GUIDELINE 1 GUIDELINE 1 GENERAL EMERGENCY G.In Plant Protective

Actions 1.Ensure personnel accountability

per EIP-I0.0.2.Plan and initiate reentry's per EIP-14.0.3.Ensure proper Control Room response.4.Assign an individual

to provide periodic plant status updates.5.Assign an individual

to maintain a log of important Emergency Director activities.

6.Assign an individual

to keep a record of all off-site communications.

___7.Determine what should be done with a unit that is not affected by the declared emergency.

Consider the effect on the emergency unit, manpower utilization, plant and grid stability, and other relevant factors.___8.In the event of mass casualties

refer to FNP-0-EIP-l1.0

step 15 to arrange for triage and additional

ambulances.

H.Off-Site Support 1.Ensure Field Monitoring

teams have been dispatched

per EIP-4.0.2.Provide information

to the EOF Manager for use in press releases and recovery planning.I.Information

to Off Site Authorities

1.Provide periodic plant status updates, meteorological

and dose estimates and release projections

based on plant conditions

and foreseeable

contingencies.

J.Re-Assess plant conditions

1.Continue to assess plant and radiological

conditions

to ensure the correct emergency classification

is declared.2.If plant and radiological

conditions

no longer require the current emergency classification

terminate the emergency class using FNP-0-EIP-28.0.

K.Long term concerns 1.Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, provide for full TSC and OSC reliefs.Page 4 of8 Version 59.0

09/28/07 13:10:44<*.:-:-GUIDELINE 1 GENERAL EMERGENCY FNP-0-EIP-9.0

GUIDELINE 1 2.Within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />, provide for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSC and OSC coverage.3.If an LOSP has occurredevaluatethe

event to ensure that an adequate supply of fuel oil is available for the Diesel Generators

for 7 days.Refer to REA 00-2337 and FNP-0-SOP-42.0

Figure 1.L.Protective

action recommendation

guidance 1.Make Protective

Action Recommendations (PARs)for all General Emergency declarations

in accordance

with NMP-EP-I09.

If an upgrade to PARS is required after making this notification

use figure 4 to transmit the new PARS to the state and county agencies.Page 5 of8 Version 59.0

MESSAGE#_FNP-0-EIP-9.0

I...J.GUIDELINE 1 GENERAL EMERGENCY RED VERBAL NOTIFICATION

FORM 09/28/07 13:10:44

2@INITIALNOTIFICATION:TIME, DATE._---:-_..:.---.:

3.SITE: FARLEY NUCLEAR PLANTU1__0/0 Power Shutdown at Time Date_/__/__U2__0/0 Power Shutdown at Time Date_/__/__D read additional

remarks on separate page fQI Under evaluation

§Above normal operating limits f9 Degrading

• Stability Class§fQI (§lEI IQINot applicableWithin normal operating limitsImprovingStable*

Precipitation

_8.EVENT PROGNOSIS:

9.METEOROLOGICAL

DATA: 7.RELEASE SIGNIFICANCE:

17.APPROVED BY: Title Emergency Director Time Date//---****Page 6 of8 Version 59.0

FNP-0-EIP-9.0

09/28/07 13:10:44*""'I.(;W'

"'1.*r

";'!,"<@:)"":.:***....j'....,..,n.'..,...*.:->>>>>:.J",<-GUIDELINE 1 GENERAL EMERGENCY RED VERBAL NOTIFICATION

FORM H.__Line 8 Event Prognosis.

Mark box A, B or C.*A should be marked if mitigation

efforts appear successful

, progressing

toward termination/recovery.*B should be marked if escalation

to a higher classification

is unlikely based on current conditions.

esc;alatlon

to a higher emergency classification

or PAR change is likely.*If stability class is not available it can be calculated

from delta temperature

from the below table i\T (200'elev.temp, OF-35'elev.temp, OF)Stability Class<-1.74 A-1.74 to<-1.56 B-1.56 to<-1.38 C-1.38 to<-0.46 D-0.46 to<1.38 E 1.38 to 3.60 F G L.__Line 12 Fill in per cent power or the time for with the event M.__Line 13 If additional

remarks are required mark the box for additional

remarks and write them on a separate paper and have them read over the ENN, or mark the box for no additional

remarks N.__The Emergency Director must sign the formwithtime and date.o.Within 15 minutes of declaration

time, using the ENN contact the state and local agencies listed below.P.__Verify the Southern LINC ENN Radio being used is turned on Q.__Ifthe Southern LINC display does not show"WIDE AREA, FEP ENN" when group is pressed in step R, THEN perform the following:

• Press the button with the square until the top line is indicated, then press the arrow buttons until"WIDE AREA" is displayed, then press the button under OK.Press thebuttonwith

the square until the second line is indicated then press the arrow buttons until"FEP ENN" is displayed, and then press the button under OK.R__Press group pushbutton, verify display shows WIDE AREA, FEP ENN.Correct per above step ifnecessary.

Pickup handset or leave in cradle, press to talk (PTT), wait for the chirp and announce"This is name/title

at Farley Nuclear Plant.Please obtain a GENERAL EMERGENCY RED initial notification

form and monitor the ENN." Release the PTT.S.__Contact one state and county agency listed in each of the four boxes below.Indicate the time of initial attempt to contact any Alabama agency.Circle agency actually contacted.

Indicate the name of the individual

contacted.

Underlined

phone numbers staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day PTT and request one Alabama agency in the order listed below acknowledge

manning of the ENN.State agency name and ask if they are on the line.Release the PTT after each request.ALABAMA State Agencies In preferred order*Alabama Radiation Control at Montgomery

EOC.ENN (1305), OPX (6628), (334-206-5391), (334-324-0076)

• AEMA ENN (1306), OPX(6619), (205-280-2312, 205-280-2310)

• Alabama Radiation Control at Alabama Forward EOC, ENN (1307), OPX 6621), (334-793-1565)

• HOUSTON COUNTY ENN (1307), OPX (6621), (334-794-9720, 793-9655, 677-4807,48082

Time N.ame---.;Acknowledged

0 Page 7 of8 Version 59.0

09/28/07 13:10:44 1°l'..'I" w O',,'

.*.."<<.....('0, l'0!...*"..**

_

GUIDELINE 1 GENERAL EMEkGENCY RED VERBAL NOTIFICATION

FORM FNP-0-EIP-9.0

Indicate the time of initial attempt to contact any Georgia agency.Circle agency actually contacted.

Indicate the name of the individual

contacted.

Underlined

phone numbers staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day PTT and request one Georgia agency in the order listed below acknowledge

manning of the ENN.State agency name and ask if they are on the line.Release the PTT after each request.GEORGIA State Agencies In preferred order*GEMA at Atlanta EOC, ENN (1304), OPX (6629), (404-635-7200)

• GEMA at Georgia Forward EOC, ENN (1308)OPX (6626), (229-723-4826)

• EARLY COUNTY, ENN(1308)OPX (6622),(229-723-3577, 3578, 4826)Time Name

0 Indicate the time of initial attempt to contact Houston County.Indicate the name of the individual

contacted.

Underlined

phone numbers staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day PTT and request Houston County acknowledge

manning of the ENN.State agency name and ask if they are on the line.Release the PTT after each request.HOUSTON COUNTY*HOUSTON COUNTY, ENN(1307), OPX (6621), (334-794-9720, 793-9655, 334-677-4807,4808)

Time Name Acknowledged

0 Indicate the time of initial attempt to contact Early County.Indicate the name of the individual

contacted.

Underlined

phone numbers staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day PTT and request Early County acknowledge

manning of the ENN.State agency name and ask if they are on the line.Release the PTT after each request.EARLY COUNTY*EARLY COUNTY, ENN(1308)OPX (6622), (229-723-3577, 3578, 4826)Time----.;Name

--.-;Acknowledged

0T.__Fill in the date and time on line 2 using the time that the fIrst state agency contact ATTEMPT was made U.__PTT and announce on the ENN"Please prepare to receive a GENERAL EMERGENCY, RED initial notification

message with acknowledgment", then slowly read the GE initial notification

form over the ENN.Release the PTT after reading two or three lines to allow individuals

to respond.V.__Have the agencies contacted above, acknowledge

receipt of the message and fill in the acknowledge

checkbox above when they do.W.__Ifany required agency could not be contacted on the ENN, then use numbers listed with each agency or in FNP-0-EIP-8.1

to contact them by any available means as soon as possible.X Fax a copy of the previous page GENERAL EMERGENCY RED VERBAL NOTIFICATION

FORM to the State of Florida, EOF using speed dial#10 Y.__Wait for the Fax report indicating

the fax was received then verify the state of Florida has received the Fax by caJ1ing (800-320-0519)

(850-413 9911)Page 80f8 Version 59.0