Text

May 2003 Exam 50-348/2003-301 Post-Exam Comments
	ML031820718
Person / Time
Site:	Farley ; (NPF-002, NPF-008)
Issue date:	07/03/2003
From:	Ernstes M; Operator Licensing and Human Performance Branch
To:	Beasley J; Southern Nuclear Operating Co
References
	50-348/03-301, 50-364/03-301 50-348/03-301, 50-364/03-301
	Download: ML031820718 (68)
	v • d • e

0. E. Grisselte

Southern Nuclear

General Manager

Operating Company, Inc.

Farley Nuclear Plant

Post Office Drawer 470

Ashford. Alabama 36312-0470

Tel 334.814.4511

Fax 334.814.4728

\\

SOUTHERN&

COMPANY

FNP-2003-0057-TRN

June 6,2003

Mr. Lee Miller

United States Nuclear Regulatory Commission

Region 11, Atlanta Federal Center

61 Forsyth St., Suite 23T85

Atlanta, GA 30303

Dear Mr. Miller:

Please find enclosed the question comments for the written examination administered at

Farley Nuclear Plant on May 30,2003, as required per NUREG 1021.

The completed examination security agreement, with the exception of the two people that

Gary Ohmstede discussed with you, is enclosed. These will be forwarded as soon as they are

received.

If you have any questions, please contact Joel Deavers at (334) 814-4853 or John Horn at

(334) 814-4652.

Sincerely,

Nu6ear Plant General Manager

Enclosure

JLD:mgr

cc:

B. D. McKinney

File

M I X DISK 5535

56. 075K1.01 001/2/2//MEM 2.5/2.5/NIFA03301/DR

Unit 1 is in the process of starting up and is currently at 25% power.

Unit 1 Circulating water pit level has dropped to 150 feet.

Which ONE of the following describes the process by which water is made up to the

Circulating Water Canal?

A. Service Water is automatically made up to the system via Circulating Water Makeup

Valve (560).

B. Service Water must be manually made up to the system via Circulating Water

Makeup Valve (560).

C. River Water is automatically made up to the system via Circulating Water Makeup

Valve (560).

D. River Water must be manually made up to the system via Circulating Water Makeup

Valve (560).

A - Incorrect; At this low power level the Circulating Water Makeup Valve (560) will be

controlled in "Remote Manual" not automatic.

B - Correct; Per OPS-52104D

C & D - Incorrect; Service water is the makeup supply to the Circ water canal, river

water is the makeup to the service water system.

Change to accept both the A and B answers as correct.

The stem of the question states that Unit 1 is starting up but does not state if the startup

is being conducted per UOP-1.2 or UOP-1.3.

UOP-1.2 States:

2.23 Circ water canal make up is being controlled manually with NlP16V748, C W

CANAL SW SUPP MANUAL ISO, or with QIP16V560 in Remote Manual per

appendix 1 of FNP-1-SOP-26.0.

UOP-1.3 has no initial conditions regarding the control of the canal makeup. It does

have a requirement to complete UOP-2.1, which states:

2.11 The Circulating Water Make-up Control Valve, QlP16V560, is in the OPEN

position, and canal level is being maintained by use of manual valve, QIP16V748,

OR

Make-up Control Valve, QlP16V560, is in the AUTO position, and canal level is

being maintained by Remote operations per FNP-1-SOP-26.0, Appendix 1.

SOP-26.0 Appendix 1 allows the canal makeup valve to be in remote manual or in

automatic operation.

Answer A. Service Water is automatically made up to the system via Circulating Water

Makeup Valve (560),

is correct if the startup is done per UOP-1.3, because service

water may be automatically made up to the circulating water canal.

Answer B.

Service Water must be manually made up to the system via Circulating

Water Makeup Valve (560). is correct if the startup is conducted per UOP-1.2 because

service water is manually made up to the circulating water canal.

Answers C and D are both incorrect because the river water system does not connect to

the circulating water canal, but it does supply water to the service water pond.

01/28/03 10:43:56

FNP- 1 -UOP- 1.2

-

2.14

1

CHEM

-

2.15

1

-

2.16

-

2.17

1

-

2.18

-I-

-

2.19

-/-

-

2.20

1

-

2.21

1

2.22

-

-/-

-- 2.23

/

-

IF the Condensate and Feedwater System was placed in wet layup,

Chemistry has verified that the system's water chemistry is within specifications.

The settings on MCB Manual/Auto station potentiometers have been verified per

the Curve Book.

The control rod drive system is aligned for normal operation per

SYSTEM.

FNP-1-SOP-41.0, CONTROL ROD DRIVE AND POSITION INDICATION

Verify the wet layup recirc filtration system has been taken out of service.

Steam generator blowdown is established at maximum flow rate allowed by

TAVG consideration.

-

IF this procedure is being performed for an initial cycle startup following a

refueling, THEN the Technical Group has verified that the prerequisites and

initial conditions of FNP-1-STP-101, ZERO POWER REACTOR PHYSICS

TESTING, have been met. (SOER88-02)

A briefing has been performed by the Senior Line Manager of all involved

personnel. This briefing requires completion of the AP-92, BRIEFING

CHECKLIST FOR THE CONDUCT OF INFREQUENTLY PERFORMED

TESTS OR EVOLUTIONS. The completed briefing form should be attached to

this procedure for document tracking purposes.

The Power Range NIS High Flux Reactor Trip setpoint is reduced to less than

or equal to 85% Reactor Power. (Ref. OR 1-97-007, NEL 96-0451 and

CMT 10485)

Prior to rod withdrawal, verify the following items on the plant computer:

2.22.1

Page 2RS2: All rods at zero steps.

2.22.2

Page 2RS3: Correct ARO limit.

0, or with QlP16V560 in Remote Manual per

-3-

Version 62.0

~

03/12/03 11:26:36

FNP-1 -UOP-I .3

FAmEY NUCLEAR PLANT

UNIT 1

UNIT OPERATING PROCEDURE UOP-1.3

STARTUP OF UNIT FOLLOWING AN

AT POWER REACTOR TRIP

1.0

Purpose

This procedure provides the Initial Conditions, Precautions, Technical Specifications and

Instructions for startup of Unit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following a reactor trip. This procedure

has been identified as involving an infrequently performed test or evolution (IPTE)

requiring Senior Line Manager oversight. Periodic monitoring by the Senior Line

Manager is required at specified steps within the body of this procedure. The Operations

Manager, or his designee may perform all functions of the Senior Line Manager for

performance of this test. Per AP-92, the designee may be an Operations Superintendent

or an individual at the manager level, or higher.

1.1

The Shift Supervisor or Plant Operator shall initial for the completion of each step

and record the date and time in the space provided by the associated step.

Initials

Datemime

1.2

plant conditions preclude the performance of any step(s) in the Instructions

Section,

Supervisor.

Instruction steps noted by an asterisk (*) are operations that do not have to be

performed in the specified sequence.

those step(s) shall be marked NIA and initialed by the Shift

1.3

2.0

Initial Conditions

__ 2.1

The version of this procedure has been verified to be the current version and

correct unit for the task. (OR 1-98-498)

--

2.2

M LOAD TO HOT

I

__ 2.3

L

__ 2.4

RCS temperature is being controlled by steam dumps or SG Atmospheric Reliefs

and the auxiliary feedwater system is being used to maintain SG level.

Reactor startup is anticipated to be within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of reactor trip.

I

Page 1 of 29

Version 44.0

03/12/03 11:26:36

FNP-I-UOP-1.3

__ 2.5

RCS Zinc concentration is < 80 ppb.

CHEM

)NOTE:

IF Comtmter Services is unable to copy the data in step 2.6 AND Operations

I

Management approves, THEN the foilbwing step maybe marked N/A.

I

__ 2.6

1

-

2.7

1

__ 2.8

I

2.9

-

1

Computer Services has been notified to make a copy and store the unit trip

history to tape. This takes approximately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to accomplish and must be

completed before performance of step 5.10.11.

A briefing has been performed by the Senior Line Manager of all involved

personnel. This briefing requires completion of the AP-92, BRIEFING

CHECKLIST FOR THE CONDUCT OF INFREQUENTLY PERFORMED

TESTS OR EVOLUTIONS. The completed briefing form should be attached to

the Official Test Copy of this procedure for document tracking purposes.

The Power Range NIS High Flux Reactor Trip setpoint is reduced to less than or

equal to 85% Reactor Power. (Ref. OR 1-97-007, NEL 96-0451 and

CMT 10485)

Prior to rod withdrawal, verify the following on the plant computer:

2.9.1

Page 2RS2: All rods at zero steps.

2.9.2

Page 2RS3: Correct ARO limit.

-I-

3.0

Precautions and Limitations

3.1

3.2

3.3

3.4

3.5

Main Steam Line Drain Pots shall be unisolated prior to rolling the main turbine.

During reactor startup, at least two licensed reactor operators shall be present in

the control room.

Criticality shall be anticipated any time the shutdown or control rod banks are

being withdrawn or when dilution operations are in progress. {CMT 0007639)

All approaches to criticality shall be guided by an inverse count rate plot per

Appendix 2. {CMT 0007640)

All shutdown rods shall be fully withdrawn before the reactor is brought to

critical condition. {CMT 0008552)

Page 2 of 29

Version 44.0

01/03/03 11:56:12

FNP-1-SOP-26.0

APPENDIX 1

APPENDIX I

SW TO CW CANAL LCV, QlP16V560, OPERATION

1.0

MCB Switch Operation

1.1

Placing the QlP16V560 MCB switch from AUTO to OPEN.

NOTE:

Placing the QlP16V560 MCB switch to OPEN fails QlP16V560 to its open

I

position.

I

Drawing A-170059, Sheet 146, may be used as a reference.

I

1.1.1 When maintenance or plant conditions require, place the QlP16V560

MCB switch to OPEN.

1.1.2 Maintain CW canal level withNlP16V748, CW CANAL SW SUPP

MANUAL ISO.

1.2

Placing the QlP16V560 MCB switch from OPEN to AUTO.

NOTE:

With the QlP16V560 MCB switch in AUTO, QlP16V560 can be controlled

automatically or manually (pneumatically) on local control panel NlP16F501.

This is accomplished by having the local control panel NlP16VF501 mode

selector switch in AUTOMATIC or MANUAL. (respectively).

Ensure Chemistry personnel are available to operate the clarifier system.

1.2.1 VerifyNlPI9V943T, AIR SUPP TO CW MKUP LVL CONT

NlP16F501, is open.

1.2.2 Verify the local control panel NlP16F501 mode selector switch is in

MANUAL.

1.2.3 Using NlP16V748, CW CANAL SW SUPP MANUAL ISO, adjust the

CW canal level to be a few inches below the upper limit.

1.2.4 Using the black knob, adjust local control panel NlP16F501 MANUAL

LOADING PRESSURE gage reading to 3 pig.

1.2.5 Place the QlP16V560 MCB switch to AUTO.

1.2.6 Using the black knob on local control panel NlP16F501, adjust

MANUAL LOADING PRESSURE gage reading to 15 psig to obtain

minimum expected position of QlP16V560 during automatic operation.

Page 1 of 6

Version 3 1 .O

01/03/03 11:56:12

FNP-

1-SOP-26.0

APPENDIX 1

NOTE: In the following steps, NlP16V748 should be closed enough to keep the clarifier

supply transfer sump (wet pit) spilling a small amount of water into the CW canal,

but open enough to allow QlP16V560 to modulate within its expected band of

3-15 psig.

1.2.7 Have Chemistry perform the following.

1.2.7.1 If possible, have both clarifier pumps in operation.

1.2.7.2 Fully open NlP16V744, SW SOV TO CLAR SUPPLY PMP

VT' handle valve), to maximize SW to the supply transfer sump

(clarifier wet pit).

1.2.8 Adjust NlP16V748 so the clarifier wet pet is spilling a small amount of

water into the CW canal.

I

-

control of QlP16V560 may cause the SWEuiergency Recirc Valves to open. 11

1.2.9

1.2.10

1.2.1 I

1.2.12

1.2.13

Using the black h o b on local control panel NlP16F501, adjust

MANUAL LOADING PRESSURE gage reading to match the

INSTRUMENT LOADING PRESSURE gage reading.

Place the local control panel NlP16F501 mode selector switch to

AUTOMATIC.

Using the black knob on local control panel NlP16F501, adjust

MANUAL LOADING PRESSURE gage reading to zero.

Verify that the CW can

canal level and res

within its expected band.

Notify Chemistry to operate the clarifier system per procedure (maintain

NlP16V744 and clarifier pumps as required).

1.2.14 Initial Cooling Tower Blow Down Operation after QlP16V560 MCB switch is

taken from OPEN to AUTO.

1.2.14.1 When CTBD is initially put on service (e.g., following an outage

or first time after a ramp downhp & QlP16V560 MCB switch is

placed from OPEN to AUTO), observe the operation of

NlP16F501.

Page 2 of 6

Version 3 1 .O

01/03/03 11:56:12

FNP-1-SOP-26.0

APPENDIX 1

1.2.14.2 Adjust NlP16V588, CTBD FCV, as necessary to allow

NlP16F501 to maintain the CW canal level with a local control

panel NlP16F501 INSTRUMENT LOADING PRESSURE gage

reading of greater than 3 psig for the duration of the blow-down.

1.2.14.3 Inform Chemistry if an adjustment ofNlP16V588 is necessary.

I

2.0

Local Control Panel NlP16F501 Automatic or Remote Manual Operation.

2.1

Shifting from Automatic Control to Remote Manual Control of QlP16V560.

2.1.1 VerifyNIP19V943T, AIR SUPP TO CW MKUP LVL CON7

NlP16F501, is open.

Verify QlP16V560 MCB switch is in AUTO.

Verify local control panel NlP16F501 mode selector switch is in

AUTOMATIC.

2.1.2

2.1.3

NOTE:

A MANUAL LOADING PRESSURE reading of 3 psig should position

QlP16V560 at approximately 75% open, which provides valve maximum flow.

A MANUAL LOADING PRESSURE reading of 15 psig equates to QlP16V560

being 25% open, which allows approximately 2000 gpm flow to pass to ensure

proper clarifier system operation.

II

readin

II

I

controlof QIP16V560 may cause the SW Emergency Recirc Valves to open. 11

2.1.4 Using the black knob on local control panel NIP16FjOl. adjust

MANUAL LOADING PRESSURE gage reading to match the

INSTRUMENT LOADING PRESSURE gage reading.

Page 3 of 6

Version 31.0

01/03/03 11:56:12

FNP-1-SOP-26.0

APPENDIX 1

2.1.5

Place local control panel NlP16F501

de selector switch to MANUAL.

2.1.6

S

2.1.7

ired position with the local

NlP16F501 black knob.

2.2

Shifting from Remote Manual Control to Automatic Control of QlP16V560.

2.2.1 VerifyNlP19V943T AIR S W P TO CW

LVL CONTNlP16

open.

2.2.2 Verify QlP16V560 MC

2.2.3 Verify local control panel NlP16V501 mode selector switch is in MANUAL.

2.2.4

Verify controller NlP16F501 indicates a supply air pressure of- 20 psig.

2.2.5 Using the black knob on local control panel NlP16F501, adjust

MANUAL LOADING PRESSURE gage reading to match the

INSTRUMENT LOADING PRESSURE! gage reading.

2.2.6 Place local control panel NlP16F501 mode selector switch to

AUTOMATIC.

2.2.7 Using the black knob on local control panel NlP16F501, adjust

MANUAL LOADING PRESSURE gage reading to zero.

ic by observing

2.2.8

3.0

Manual Jacking Operation with the Actuator Handwheel

Page 4 of 6

Version 31.0

01/03/03 11:56:12

CAUTION:

WHEN manually jacking QlP16V560 closed,

approximately 25% open due to mechanical blocks that are internal to the

actuator.

it cau only be positioned

CAUTION:

W H E N manually jacking Q1P16V560 open, THEN for design considerations

only position the valve to a maximum Of 75% open as indicated on the

circular dial on the actuatorm thc indication marked on the stem. Use

caution because the valve can be positioned to greater that 75% open by

backing out the actuator handwheel too far.

-

FNP-1-SOP-26.0

APPENDIX 1

TOTE: 0

Prior to jacking QlP16V560 with the handwheel on the actuator, loosen the

locking nut on the actuator stem.

After jacking QlP16V560 to the desired position, tighten the locking nut on

the actuator stem.

The wrench size needed for the actuator locking nut is 1% inches.

The actuator stem for the handwheel and locking nut has left handed threads;

therefore, when looking down on the actuator and handwheel, turning the

handwheel counter clockwise closes QlP16V560 and turning the locking nut

counter clockwise will tighten the locking nut.

0

3.1

Placing QlP16V560 On the Actuator Handwheel Jack

3.1.1 Place the QlP16V560 MCB switch to OPEN.

3.1.2

In the valve box, verify that QlP16V560 has failed to its fully open

position (approximately 75%

indication marked on the stem).

3.1.3

Close NlP19V152C, IA to QlP16V560.

3.1.4 Manually jack QlP16V560 to its desired position.

3.2

Taking QlP16V560 Offthe Actuator Handwheel Jack

3.2.1

Check the QlP16V560 MCB switch in OPEN.

3.2.2

At local control panel NlP16F501, verify the mode selector switch is in

MANUAL.

3.2.3 Using the black knob, adjust local control panel NlP16F501 MANUAL

LOADING PRESSURE gage reading to 3 psig.

Page 5 of 6

Version 31.0

01/03/03 11:56:12

FNP-1-SOP-26.0

APPFNnlX 1

l ( c A ~ T ~ N ~ S t e p s

3.2.4 through 3.2.8 should be performed expeditiously to ensure CW

cnnal level is maintained at tbe Droner level.

3.2.4 Manually jack QlP16V560 to the fully open position (approximately 75%

-

OR indication marked on the stem).

OpenNlP19V152C, IA to QlP16V560, and observe -80 psig k 5 psig on

N1P 16PI560C.

3.2.6

Place QlP16V560 MCB switch in AUTO.

3.2.5

NOTE:

3 PSI = 75% open and 15 PSI = 25% open.

I

3.2.7 Place QlP16V560 to desired position to control CW canal level with local

control panel NlP16F501 black knob.

3.2.8

desired to place QlP16V560 in automatic control, THEN proceed to

section 2.2 of this appendix.

Page 6 of 6

Version 3 1 .O

63. G2.1.22 00 1/3/iMODE/C/A 2.8/3.3iNiFA03301WSDR

Which ONE of the following Mode changes requires at least two (2) mode determination

parameters to change?

(Mode determination parameters are Reactivity Condition (Keff), Rated Thermal Power,

Average Coolant Temperature).

A. Going from Mode 1 to Mode 2.

B. Going from Mode 5 to Mode 4

C. Going from Mode 3 to Mode 2.

D. Going from Mode 5 to Mode 6.

Reference Technical Specification Definitions Table 1.1-1.

Distractor Analysis:

A: Incorrect, Difference between Mode 1 and Mode 2 requires only % Rated Thermal

Power to change.

B: Incorrect, Difference between Mode 5 and Mode 4 requires only Average Coolant

Temperature to change.

C: Incorrect, Difference between Mode 3 and Mode 2 requires only Reactivity Condition

(Keff), to change.

D: Correct, Difference between Mode 5 and Mode 6 requires both Reactivity Condition

(Keff), and Average Coolant Temperature to change.

This question should be deleted due to no correct answer.

A. This answer is incorrect for reasons stated above.

B. This answer is incorrect for reasons stated above.

C. This answer is incorrect for reasons stated above.

D. Incorrect, the Mode change parameters are Keff, Temp and power. Power is not

required to be changed. Temperature is not required to change to enter mode 6

either by tech specs or plant procedure. Temperature is required to be at 140°F for

fuel movement but not to detension the reactor head. Mode 6 is defined by the table

as the reactor vessel head less than fully tensioned. RCS boron is required to be at

2000 ppm prior to entering Mode 6 but is not listed in the stem as a mode change

parameter. This specification does not require a specific change to Keff for Mode 6

entry, only minimum RCS boron concentration that could also be met in Mode 5.

See table below from Tech Specs.

Table 1.1-1 (page 1 of 1)

MODES

MODE I

TITLE

1

Power Operation

2

Startup

3

Hot Standby

Hot Shutdown(b)

5

Cold Shutdown@)

6

Refueling(c)

REACTIVITY

CONDITION

(keff)

2 0.99

< 0.99

NA

Yo RATED

THERMAL

POWER(a)

> 5

5 5

NA

AVERAGE

REACTOR COOLANT

TEMPERATURE

(" F)

NA

t 350

350 > Taus > 200

5 200

NA

(a)

Excluding decay heat.

(b)

(c)

All reactor vessel head closure bolts fully tensioned.

One or more reactor vessel head closure bolts less than fully tensioned

03/12/03 11:26:57

FNP-1-UOP-4.1

FARLEY NUCLEAR PLANT

UNIT 1

UNIT OPERATING PROCEDURE UOP-4.1

CONTROLLING PROCEDURE FOR REFUELING

1.0

Purpose

This procedure provides the Initial Conditions, Precautions, Limitations and Instructions

for refueling the reactor in a safe manner.

NOTE:

At the completion of each step, a person from the designated group, the SRO in

charge of fuel handling , a Plant Operator, the Shift Support Supervisor or the

Shift Supervisor shall initial

by the associated step as follows:

record the date and time in the space provided

Initials

DatefI'ime

Only the Shift Supervisor, the SRO in charge of fuel handling, or a person from

the designated group (with Shift Supervisor concurrence) may mark a step N/A

if it is not to be performed. Steps marked N/A shall be justified and approved by

the Shift Supervisor in accordance with the requirements of FNP-0-AP-6,

PROCEDURE ADHERENCE.

2.0

Initial Conditions

NOTE:

Initial Condition 2.29 must be completed prior to lowering RCS water level to

the vessel flange (step 4.1.9).

Initial Condition 2.7 must be completed prior to Mode 6 (Step 4.1.12).

I

Initial Conditions 2.22 and 2.23 must be completed prior to Reactor Vessel Head

lift (Step 4.1.20 or 4.1.26).

Initial Conditions 2.12,2.17,2.18,2.25, and 2.28 must be completed prior to

flood up (Step 4.1.29).

Initial Conditions 2.9,2.13.3,2.13.4,2.19,2.22,2.27, and 2.28 must be completed

prior to rod unlatching (Step 4.1.30) and upper internals lift (Step 4.1.32).

All Initial Conditions must be completed prior to fuel assembly movement

(Step 4.1.35).

Date/Time

__ 2.1

L

correct unit. (OR 1-98-498)

The version of this procedure has been verified to be the current version and

-1-

Version 24.0

03/12/03 11:26:57

FNP-1-UOP-4.1

DateITime

-

2.2

L

-

2.3

1

A Fuel Assembly Transfer Form or an approved Westinghouse Refueling

procedure with a fuel transfer form has been issued.

A full core offload is specified by the Fuel Assembly Transfer Form or approved

Westinghouse refueling procedure with a fuel transfer form.

is NOT to be performed, THEN initial condition 2.3.1 must be met.

a full core offload

-

2.3.1

a fuel shuffle is being performed,

specific guidance on

1

intermediate fuel locations has been incorporated into the refueling

sequence.

NOTE:

The guidance for intermediate fuel locations is stated in section 3.17 of

FUEL ASSEMBLIES. This guidance only applies to full core offloads. For a

fuel shuffle, additional guidance would have to be developed and incorporated in

the refueling sequence.

FNP-0-FW-7.0, LIMITATIONS AND PRECAUTIONS FOR HANDLING

__ 2.4

1

RF

coordinator

-

1

Component Movement section.)

WEST

__ 2.5

-/-

RF

coordinator

The refueling procedure contains guidance for intermediate fuel locations,

temporary storage of fuel assemblies and all appropriate refueling personnel

including Westinghouse personnel have been trained on this guidance and the

potential consequences of violating this guidance.

(Refer to Westinghouse refueling procedure, Fuel Assembly and Core Compound

The refueling procedure contains the following guidance to prevent

misalignments and subsequent abnormal gaps. Document performance of steps

2.5. I thru 2.5.5 by initialing step 2.5.

-

1

WEST

-/-

-

ES

I

2.5.1

Load no more than one-half of a row in the same direction, to the

extent practicable. Exceptions may be granted by PRl3 approval of the

Refieling Procedure.

When completing rows (Le., loading the last assembly in a row,

adjacent to the baffle), complete the third row out from the baMe first,

the second row out from the baffle next, and the baffle row last.

2.5.2

-2-

Version 24.0

03/12/03 11:26:57

FNP-I-UOP-4.1

2.5.3

Inspect for non-uniformity or substantial misalignment after each fuel

assembly is seated, and for assemblies locked out of alignment by the

mechanical interaction of crossing rows of assemblies.

Inspect all assembly-to-assembly gaps, assembly-to-baffle gaps, and

all top nozzle comer-to-comer junctions during core verification.

If misalignments exist, determine the source of the misalignment.

Using normal fuel handling procedures, remove designated assemblies

and reseat them in the core as appropriate. Reinspect all gaps and

misalignments that may have been changed by reseating assemblies.

2.5.4

2.5.5

Perform F"-1-STP-13.0, REACTOR DECAY TIME, to verify reactor has been

subcritical for at least 140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months .

in the last 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months per SR 3.9.1.1 prior to the start of head stud detensioning.

Deleted

The containment building penetrations are in the following status within 100

hours prior to the start of core alterations.

2.9.1

The equipment door closed and held in place by a minimum four bolts.

2.9.2

A minimum of one door in each air lock is closed.

2.9.3

Each penetration providing direct access from the containment

atmosphere (except pens 71,72,90, and 92 which are addressed in

step 2.9.4) shall be either closed by an isolation valve, blind flange or

manual valve per FNP-1-STP-18.4, CONTAINMENT MID-LOOP

AND/OR REFUELING INTEGRITY VERIFICATION AND

CONTAINMENT CLOSURE,

operable automatic containment purge and exhaust isolation valve as

tested per FNP-1-STP-18.1, CONTAINMENT PURGE AND

EXHAUST ISOLATION TEST MODES 5 & 6.

capable of being closed by an

-3-

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FNP-1-UOP-4.1

NOTE:

Water or air lines which penetrate through the adapter nozzles must be

pressurized or isolated with their individual isolation valves.

I

-

1

2.9.4

Blind flanges are installed at CTMT penetrations 71, 72, 90, and 92,

-

OR the special adapter nozzles for these penetrations are installed.

-

2.9.5

FNP-1-STP-18.4, CONTAINMENT MIDLOOP AND/OR

-I-

REFUELING INTEGRITY VERIFICATION AND CONTAINMENT

CLOSURE, has been reviewed and verified to satisfy refueling

integrity.

A caution sign concerning the establishment of containment integrity

has been posted in the following locations:

2.9.6

I NOTE:

The signs can be obtained from the Shift Support Supervisor and are normally I

I

_ _

storedin the Unit 2 CCW Storage Room.

-

I

2.9.6.1

Personnel Access Hatch

2.9.6.2

Auxiliaty Access Hatch

2.9.6.3

139' Electrical Penetration Room

2.9.6.4

121' Piping Penetration Room

2.9.6.5

100' Piping Penetration Room

2.9.6.6

Main Steam Valve Room (both entrances)

-4-

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FNP-1-UOP-4.1

2.10

Deleted

NOTE:

a One SFP cooling loop is required to be in service and the purification loop

should be maintained in service as much as possible. The skimmer loop may

be used as desired for surface cleanup.

The Tri Nuclear Filter System may be considered as a purification loop for

the purposes of the following initial condition.

The spent fuel pool cooling and purification system is aligned and in operation

with at least one cooling and purification loop in service per FNP-1-SOP-54.0,

SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM or

FILTER SYSTEM. The skimmer loop may be used as desired.

The RCS has been purified to meet the requirements of FNP-0-CCP-202,

WATER CHEMISTRY SPECIFICATIONS, and FNP-1-CCP-203, CHEMISTRY

AND ENVIRONMENTAL GROUP CONSIDERATIONS DURING

OPERATIONAL TRANSIENTS before mixing with the RWST; and other

chemistry is within limits or as specified by the Chemistry Supervisor.

The following radiation monitors are in operation per FNP-1-SOP-45.0,

RADIATION MONITORING SYSTEM, or required action is being taken per

Tech. Specs 3.3.6,3.3.7, and 3.3.8, and TR 13.3.4.

2.13.1

__ 2.1 1

-

/

FNP-0-SOP-54.3, SPENT FUEL POOL CLEANUP USING TRI NUCLEAR

-

2.12

-

I

CHEM

2.13

-

/

R-5 Spent fuel pool or portable monitoring instrumentation used

to monitor SFP area at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

R-25A or B Spent fuel pool - Gaseous

2.13.2

-

I

in operation.

__

2.13.4

R-35A or B - Control Room HVAC.

2.13.3

R-24A or B - Containment purge system with main or mini purge

I -

-

2.14

-

/

The fuel handling area W A C is in operation per FNP-1-SOP-58.0,

AUXILIARY BUILDING HVAC SYSTEM.

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FNP-1-UOP-4.1

The direct communications system between the below listed stations is

verified available for use within one hour prior to fuel movement.

2.15.1

Control Room

2.15.2

Manipulator Crane

2.15.3

2.15.4

Spent fuel pool side fuel transfer system control panel.

Reactor side fuel transfer system control panel.

Fuel assembly status board is available in the control room.

The manipulator crane gripper has been load tested within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to

movement of fuel assemblies per FNP-1-STP-36.0, MANIPULATOR CRANE

CUTOFF AND LOAD TEST. (Required prior to Cavity flood up, OLL 1848)

The manipulator crane auxiliary hoist has been load tested within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months of

movement of control rods per FNP-1-STP-36.0, MANIPULATOR CRANE

CUTOFF AND LOAD TEST. (Required prior to Cavity flood up, OLL 1848)

The Reactor Cavity water level is 2 1422 ( 2 23 feet over the top of the

irradiated fuel assemblies seated in the core) within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to movement of

control rods within the reactor pressure vessel.

The Spent Fuel Pool water level is 2 15 16 ( 2 23 feet over the top of irradiated

fuel assemblies seated in the storage racks).

Two independent penetration room filtration systems are verified aligned to the

spent fuel pool room prior to fuel handling or crane operations in the spent fuel

storage room per FNP-I -STP-20.1, PENETRATION ROOM FILTRATION

ALIGNMENT VERIFICATION. Otherwise, comply with actions of Tech Spec 3.7.12.

The direct communications system between the control room and the

reactor cavity is verified available for use within one hour prior to latching or

unlatching control rods OR installing or removing upper internals.

-6-

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FNP-1 -UOP-4.1

__ 2.23

The Controlled Refueling Area Boundary (CRAB) has been established as

appropriate per FNP-0-ACP-7.0, FOREIGN MATERIAL EXCLUSION

FAC

PROGRAM.

2.24

Deleted

__ 2.25

Verify life ring is available at cavity area prior to flooding cavity.

I

__ 2.26

-

/

Ensure vital shared equipment is aligned to Unit 2 as follows:

-

IF the outage will involve reducing the availability of offsite power to the IF or

1 G 4 160V buses,

place or verify the following loads on Unit 2 per FNP-1-

SOP-36.3,600,480 and 208/120 VOLT AC ELECT DISTRIBUTION SYSTEM:

1F 600 V MCC

1G 600 V MCC

1-2K 600 V LC

1-2L 600 V LC

2.27

Verify at least two of the required source range neutron flux monitors are

operable with continuous visual indication in the Control Room and a channel

check performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to any core alterations. Trip functions and

associated TSLBs are not required for Mode 6 or core alterations.

2.27.1 Source Range Nuclear Instrument, Channel N-31

2.27.2 Source Range Nuclear Instrument, Channel N-32

2.27.3 Gamma-Metrics Neutron Flux Monitor, Channel N-48

NOTE:

The Scaler-Timer may be verified to be operating properly by performing an

operational check per SOP-39.0. If performed, then ensure it is restored to a

normal alignment.

-1-

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FNP-1-UOP-4.1

-

2.28

At least one source range nuclear instrument charnel N-3 1 or N-32, has an

audible count rate in the control room or in containment using a stationed licensed

operator who will communicate with control room if required to alert them of a

possible dilution accident.

NOTE:

Step 2.9 may be performed at the same time as step 2.29.

I

2.29

Prior to lowering the reactor coolant water level to the vessel head flange

following reactor shutdown, perform the following:

-

2.29.1

Perform a containment integrity assessment for Mid-Loop integrity

and

maintain the assessment current per one of the following methods.

2.29.1.1

Perform Mid-Loop Integrity assessment for Mid-Loop

integrity per FNP-1-STP-18.4, CONTAINMENT IWD-

LOOP AND/OR REFUELING INTEGRITY

VERIFICATION AND CONTAINMENT CLOSURE.

OR

2.29.1.2

For the initial draindown to the vessel head flange

following reactor shutdown an assessment may be

performed based on maintenance released which could

potentially impact midloop integrity. To maintain a valid

assessment administrative controls (LCO tracking sheet)

will be maintained to ensure the assessment is revised to

reflect any changes to the penetrations subsequent to the

performance of the assessment.

-

2.29.2

A Maintenance Closure Response Team (MCRT) is staffed and

briefed

with sufficient personnel, having the necessary tools and procedures

staged, to facilitate rapid closure of the CTMT Equipment Hatch. This

crew is normally staffed by the maintenance crew assigned to reactor

disassembly. The MCRT Leader is identified to the MCR staff to

ensure rapid notification if a loss of RHR event were to occur.

2

MM

NOTE:

Appendix 3 is meant to be a guide and can be changed by the Outage Manager I

~

-

I

depending on special plant conditions.

I

-

2

the Outage Manager.

2.29.3

Appendix 3 has been approved and appropriately distributed by

-8.

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.i^

FNP-1-UOP-4. I

-

L

2.29.4

A briefing has been performed by the Senior Line Manager of all

involved personnel. This briefing requires completion of the AP-92,

BRIEFING CHECKLIST FOR THE CONDUCT OF

INFREQUENTLY PERFORMED TESTS OR EVOLUTIONS. The

completed briefing form should be attached to this procedure for

document tracking purposes. Draining to the vessel flange (1297) or

mid plane (1233 to 1235) will be designated an IPTE and require

Senior Line Manager Oversight. (IN-97-83)

__ 2.30

RCS temperature < 140°F.

-/-

__ 2.31

-I-

RF

coordinator

3.0

Precautions and Limitations

Training has been completed on recent refueling equipment design changes

for the appropriate personnel. (Commitment 94- 13-01)

3.1

At least two source range neutron flux monitors shall be operating, each with

continuous visual indication in the control room

one channel of audible

count rate in the control room or in containment using a stationed licensed

operator that will communicate with control room if required to alert them of a

possible dilution accident.

The Gamma-Metrics source range channel may only be used as a back-up to N-31

or N-32 during certain core configurations. The Refueling Coordinator or

Westinghouse should be consulted if N-3 1 or N-32 becomes inoperable when the

core is not fully loaded.

The High Flux at Shutdown alarm serves as an additional monitor of neutron flux

during stable flux conditions. During core reload, continually changing neutron

flux is being closely monitored by performance of a 1/M plot. The High Flux at

Shutdown alarm may be placed in the BLOCK position to prevent spurious

alarms in containment.

3.2

3.3

3.4

the High Flux at Shutdown alarm is actuated,

all personnel will

evacuate the containment in an orderly manner. @the alarm is actuated during

movement of fuel, =return

the he1 to the position it occupied prior to the

alarm before evacuating the containment.

-9-

Version 24.0

Definitions

1.1

Table 1.1-1 (page 1 of 1)

MODES

TITLE I

1

Power Operation

2

Startup

3

Hotstandby

Hot Shutdown(b)

Cold Shutdowdb)

6

Refuelin&

REACTIVITY

CONDITION

(Ihd

2 0.99

< 0.99

NA

% FMTED

THERMAL

POWER(^)

> 5

s 5

NA

AVERAGE

REACTOR COOLANT

TEMPERATURE

(" F)

NA

2 350

350 >Taw > 200

5 200

NA

(a)

Excluding decay heat

(b)

c)

All reactor vessel head closure bolts fully tensioned.

One or more reactor vessel head closure b l t s less than fully tensioned.

Farley Units 1 and 2

1.1-7

Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Boron Concentration

3.9.1

SURVEILLANCE

SR 3.9.1.1

Verify boron concentration is wlthln the limit specified

In COLR.

3.9 REFUELING OPERATIONS

3.9.1 Boron Concentration

FREQUENCY

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

-co 3.9 1

Boron concentrattons of the Reactor Coolant Svstem. the relbelina canal

and the refuellnq caVltv shall be malntalned within the Ilm t specified in the

COLR.

APPLICABILITY:

MODE 6,

ACTIONS

Suspend CORE

within limit.

ALTERATIONS.

Suspend positive

reactivity additions.

Initiate action to restore

boron concentration to

within limit.

COMPLETION TIME

Immediately

immediately

Fariey Units 1 and 2

3.9.1-135

Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

\\

L.

2.7

CORE OPERATING LIMlTS REPORT, FNP UNIT 1 CYCLE 18, REV. ZDECEMBER 2001

I

Nuclenr Enthalov Rise Hot Channel Factor - FL, (Specification 3.2.2)

2.7.1

F:,

<Fr%(l+PFM*(l-P))

THERMAL POWER

RATED THERMAL POWER

where:

P =

2.7.2

F

r

= 1.70

2.7.3

PF,, = 0.3

Axial Flux Difference (Specification 3.2.3)

2.8.1

2.8

The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 3

2.9

Boron Concentration (Specification 3.9.1)

2.9. I

QLLcior Core Safetv Limits for THERMAL POWER (Specification 2.1.1)

1. IO. I

The boron concentration shall he gve.?rer &?E cr eqnz! tz 2%

pi.%.'

2.10

In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System

t KCS I hi~hest loop average temperature, and pressurizer pressure shall not exceed the safety

limit% spccified in Figure 8.

2.1 I

Kc:~ior Trip Sy\\tvni l~tgtrumentation Overtemperature AT (OTATI and Ovemower AT(0PAT)

'ieiixuni 1';s:tnkwr V:ilues for Table 3.3.1-1 (Specification 3.3.1)

2. I I. I Thc Kcacior Trip System Instrumentation Oveltemperature AT (OTATJ and Overpower AT

IIWJI~

,Scipoin~ Pmamerer Values for TS Table 3.3.1-1 are listed in COLR Tables 2 and 3.

2.12

KCS I)NH I':ir;imc!cr\\ lor.Prrssurizer Pressure, RCS Average Temoerature, and RCS Total Flow

K;w 1Spl.cili<:ttwn 3.4.1 )

2. 12, I KC'S I)NU Pwnniems for Pressurizer Pressure, RCS Average Temperature, and RCS Total

Fhw K : w ~liiill

he within the limits specified below:

,.

h.

c.

I'rcwurizer pressure 2 2209 psig;

KCS :ivcmgc temperature 5 S80.3"F; and

The minimum RCS total flow rate shall be 2 263,400 GPM when using the precision

bent halancu method and 2 264.200 GPM when using the elbow tap method.

'

This concentration hounds die condition of 14~5

0.95 (:ill rods in less the most reactive rod) and

subcriticality

rods out) over the entire cycle, This concentration includes additional boron to

address uncertainties and B"' deoletion.

Page 4 of 15

71. WlE03EK3.4 001 I1 12llMEM 3.513.9lBIFA03301lRDR

A failed open spray valve that could not be shut resulted in a safety injection. The

reactor coolant pump in the affected loop was tripped and, with pressurizer pressure

now under control, safety injection termination was permitted. With only one charging

pump running, pressurizer pressure remained stable.

At the procedural step when normal charging was established, PFZR level started

trending down from 15% level and could not be controlled.

Which ONE of the following describes the actions the operator should take at this point?

A. Manually SI and recommend transitioning to EEP-0, Reactor Trip or Safety Injection.

B. Realign HHSl flow; start additional charging pumps, and recommend transitioning to

EEP-0, Reactor Trip or Safety Injection.

C. Realign HHSl flow, start additional charging pumps, and recommend transitioning to

EEP-1, Loss of Reactor or Secondary Coolant.

D. Realign HHSl flow; start additional charging pumps, and recommend transitioning to

ESP-I .2, Post LOCA Cooldown and Depressurization.

Source: Farley Exam Bank Question #ESP-I .I-52531 E06 005

References: ESP-I .I

A - Incorrect; If PZR level can not be maintained, the flow path must be reestablished

and a transition to ESP-I .2 is warranted. There is no need to manually SI and transition

to EEP-0.

B - Incorrect; the transition to EEP-0 is incorrect.

C - Incorrect: the transition to EEP-1 is incorrect,

D - Correct; From ESP-I. 1, SI Termination, if PZR level can not be maintained, the flow

path must be reestablished and a transition to ESP-1.2 is warranted.

There are two correct answers to this question:

D.

Realign HHSl flow; start additional charging pumps, and recommend

transitioning to ESP-I .2, Post LOCA Cool-down and Depressurization.

This was the examination key answer based on the fact that the SS may wait on

the OATC to regain flow to the PZR to restore PZR level. If the candidate assumes that

they establish normal charging at that moment and waits on the step to be completed,

then they would see the PZR level dropping and would attempt to recover by raising

charging flow. In this case they would utilize the RNO column of ESP-1.1, step 10.2.3

to deal with the problem and go to ESP-1.2, or the team could use ESP-0.0,

REDIAGNOSIS to get to EEP-1. Either way would be acceptable.

the procedure, are: This procedure is entered based on Operator judgment.

The purpose as designated in ESP 0.0: This procedure provides a mechanism to allow

the operator to determine or confirm the most appropriate post accident recovery

procedure with SI in progress or required.

The Symptoms or Entry Conditions of ESP-0.0, REDIAGNOSIS, as stated in

The key word in the stem is Should, (Le., the actions the operator should take)

at this point. There are several flow paths that could be taken and should is subjective,

not a mandatory. This leaves the operator to take what he thinks is the best course of

action, which in this case, not knowing what the event is, may be to go to a procedure

(ESP-0.0, REDIAGNOSIS) that will lead you to either EEP-2, EEP-3, EEP-1 and then

to ESP-1.2 or some other contingency procedure as needed.

Answer C is also a correct answer that describes actions the operator could take.

C. Realign HHSl flow, start additional charging pumps, and recommend transitioning to

EEP-1, Loss of Reactor or Secondary Coolant.

With a failed open spray valve the RCP is required to be secured. Indications

following the reactor trip and safety injection are normal through the diagnostics of EEP-

0 and the subsequent steps of ESP-I .I,

SI termination. The stem of the question

indicates the team is at step 10.2.3 which says, Establish charging flow to maintain

pressurizer level 15-50%. The team would be in the process of accomplishing this task

as the SS continues on. In SOP-0.8 the definition of Establish is, To make

arrangements for a stated condition. Example: Establish normal charging. Establish is

also not listed as a Continuing Action word.

The team is still continuing through ESP-I .I

and after step 11 which secures

RHR, the team enters step 12 which has the operator check pressurizer level

GREATER THAN 7%. The stem says the operator cannot control PZR level at this

point.

There are no radiation alarms, containment moisture alarms or containment

sump problems. The team has no indications of anything going on other than PZR level

dropping. The operator would have two options at this point:

1 . Assume the PZR level cannot be restored and is trending to 7%, use the

RNO column to re-establish HHSI flow and then transition to EEP-1 per step

12.2 RNO

2. Due to the unexplained loss of level and needing an SI and a procedural flow

path, enter REDIAGNOSIS, ESP-0.0, based on Operator judgment, which

would lead you to EEP-1.

OR

A simulator examination scenario was utilized for this class that recognized

REDIAGNOSIS as a viable option under similar conditions. This examination placed

the team in a situation at step 6 with pressure dropping and the crew entered

REDIAGNOSIS to get to EEP-1, a highly probable and also correct way to go. This is

the designed purpose of ESP 0.0 and answer C describes the actions the operators

would take from this guidance.

01/09/03 11:35:58

Defeat

Depress

Determine

Direct

Dispatch

Dump

Energize

Equalize

Establish

Evacuate

FNP-0-SOP-0.8

ATTACHMENT 1

GLOSSARY OF TERMS AND ACTIONS VERBS

To disable an automatic system or an input to a control circuit.

Example: Defeat automatic closure of the main feedwater bypass

valves.

To actuate a pushbutton device.

Example: Depress HOME key.

To calculate or evaluate using equations or graphs.

Example: Determine maximum venting time.

To order that an action be taken.

Example:

To send personnel to perfom a task outside the control room.

Example: Dispatch personnel to locally restore AC power.

Direct Chemistry to sample SGs for activity.

To release steam in a controlled manner.

Example: Dump steam to condenser.

To supply electric power to.

Example: Energize pressurizer heaters.

To make the value of a parameter the same as the value of a second

parameter.

Example:

To make arrangements for a stated condition.

Example: Establish normal charging.

To cause personnel to leave a specified area.

Example:

Equalize charging flow and letdown flow.

Evacuate affected portions of the AUX BLDG.

Page 3 of 8

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FNP-0-SOP-0.8

3.3

3.4

Notes or caution statements are placed just prior to the step to which they apply.

If a note or caution step applies to a sequence of steps, it is placed just prior to the

first step in the sequence. Any note or caution statement which applies to an

entire procedure is placed prior to the first operator action step.

Since notes and caution statements provide information needed to support proper

performance of the operator action steps, each note or caution statement must be

read and understood prior to performing the applicable steps. When the user is

directed to a specific ERP step, he must always read and understand any notes or

caution statements applicable to that step.

Terms and Action Verbs

To ensure correct performance, directed action verbs used in the ERPs are

restricted to a specific defined set. These verbs and other special terms are

presented in Attachment 1.

Step Performance

The operator action steps are arranged in a two column format. The left column

is the ActionExpected Response (AER) column. The right column is the

Response NOT Obtained (RNO) column. The expected operator actions are

presented in the A E R column in the order of performance. If the step cannot be

performed or the specified condition is not met, the user shall go to the RNO

column for that step and take the action(s) described. AAer the action steps in the

RNO column have been performed or if they cannot be performed, the user

should return to the A/ER column for the next action step. The user should keep

in mind any actions which could not be performed and complete them later as

appropriate.

The operator action steps in both the AER and RNO columns are normally

required to be performed sequentially in the numerical order specified. High

level action steps will always be numbered. If the order of performance of a

group of high level action steps is not important, this would be specifically stated

in a note prior to the first step in the group. Substeps will be numbered if the

order of performance is important. If the substeps may be performed in any order,

the substep will have a bullet ( 0 ) instead of a number.

Once the user has initiated action to accomplish an action steu, he should

the actions he has

mpleted, a note or caution statement is placed prior to the

If two steps should be performed simultaneously instead of

sequentially, a note or caution statement is placed prior to the first step to alert the

user.

-3-

Version 7.0

01/09/03 11:35:58

FNP-0-SOP-0.8

3.8

3 .o

3.10

Following verification of immediate actions, the Shift Supervisor will proceed

expeditiously to implement subsequent actions. If the UO is not in the Control

Room when an event occurs, performance of the immediate actions by the OATC

alone is sufficient. Concurrent with starting subsequent actions, the shift

supervisor should ensure the UO or another licensed operator responds to assist in

the implementation of the ERP.

Continuous Actions (CMT0008169)

Certain operator actions provided in a procedure

performance throu

generally remains applicable throughout its associated procedure unless otherwise

stated, and may apply after a transition is made to another procedure if it does not

contain any actions that are inappropriate for the subsequent procedure. For

example, a transition contained within a continuous action will not apply after a

transition is made to a RED or ORANGE path Functional Restoration Procedure

or the ECP-0 series. Furthermore, actions requiring equipment to be started

should not be performed in the ECP-0 series unless directed in that series.

Additionally, Optimal Recovery Procedure actions are not to be performed while

a Critical Safety Function is being restored from a RED or ORANGE condition.

FOLDOUT pages also identify continuous actions that apply only in their

associated procedure.

Status Determination

Two types of status determination steps are used in the Ems. The first type of

step uses the verb "check". The intent of this step is to determine if a condition

exists and then take the appropriate directed action based on this determination.

The second type uses the verb "verify". The intent of this step is to determine if a

condition exists and then take the required actions to achieve the condition if it

does not exist.

Branching

Three types of branching are possible when using the ERPs. The first type is a

branch to another step within the same ERP. If the step being branched to

precedes the step in effect, the verb "return" is used. If the step being branched to

follows the step in effect, the verb "proceed is used. The second type of branch

is a branch to a different ERP. The verb "go" is used to direct branching to a

different ERP. If the branch does not specify a step number with the ERP

number, the user is expected to begin with the first step. The third type of

branching is a branch to the Severe Accident Management Guidelines (SAMGs).

Branching to the SAMGs is covered in detail in ATTACHMENT 2.

-5-

Version 7.0

NP-1-ESP-1.1

SI TERMINATION

CAUTION: To ensure adequate supply voltage to all class 1E loads and to meet

short circuit analysis constraints, only one air compressor, 1C

(preferred) or lA, should be powered from the diesel generator. One

air compressor will consume 0.16 MW of diesel generator load.

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Revision 17

7

Verify 1C air compressor i n

7

Align 1A air compressor for

service.

service as follows.

7 . 1

Verify 1C air compressor

handswitch in RUN/START.

7.2 Verify 1 C air compressor

started.

a) Verify 1C air compressor

handswitch in OFF.

b) Verify SI - RESET.

[I MLB-1 1-1 not lit

[] MLB-1 1 1 - 1 not lit

CAUTION:

offsite power is l o s t after sequencer is reset.

THEN manual actions may be required to restart safeguards equipment.

, * f f f * * * * * * * * * * * * * L * * l * l t l t l * * * * * * t * * * * * * * * * * * * * * ~ * * * * * ~ . ~ * * * * * * * * * * * * * * * * * * * * * * *

c) Reset B1F sequencer by

depressing the ESS STOP

RESET pushbutton on the

sequencer panel.

(139 ft, AUX BLDG A train

SWGR room)

d )

Place BKR DF13 SYNCH SWITCH

in MAN.

e) Close BKR DF13 (1F 4160 V

bus tie to 1 H 4160 V bus).

Step 7 continued on next page

__ Page Completed

Page 4 of 50

FNP-1-ESP-1.1

NOTE :

Plant conditions may dictate establishment of contingency electrical

lineups. FNP-1-AOP-5.1. CONTINGENCY ELECTRICAL ALIGNMENTS provides

guidance for establishing those lineups.

SI TERMINATION

Revision 17

8.1 Check offsite power -

AVAILABLE.

8.1 Direct switchboard operator to

begin efforts to restore

offsite power.

8.2 Check BKR DFOl (1A startup

8.2 Verify 1 F 4160 V bus energized

transformer to 1F 4160 V bus)

- CLOSED.

generator.

by 1-2A or 1C diesel

8.3 Verify BKR OF02 (1F 4160 V bus

8.3

diesel generator cooling

tie to 1K 4160 V bus) -

NOT supplied from Unit 2,

CLOSED.

THEN secure 1-2A and/or 1C

diesel generator using

ATTACHMENT 1. SECURING A

DIESEL GENERATOR WITH A SAFETY

INJECTION SIGNAL PRESENT.

Step 8 continued on next page.

-Page

Completed

Page 5 of 50

FNP-1-ESP-1.1

8.7 Check 1E 4160 V bus

ENERGIZED.

SI TERMINATION

Revision 17

8.7 Establish power to 1C 600 V LC

emergency section loads.

8.7.1 Verify pressurizer heater

group 1B - OFF.

8.7.2 Open BKR EC08-1.

8.7.3 Close BKRs EE07-1 and

I

EC10-1.

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

CAUTION: To prevent diesel generator overloading, at least 0.3 MW of diesel

generator capacity must be available prior to energizing a group of

pressurizer heaters.

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

8.7.4 Energize pressurizer heater

group 1B as required.

8.8 Proceed to step 8.10.

8.9 a 1D 4160 V bus energized.

-

THEN proceed to step 9.

Step 8 continued on next page.

-Page

Completed

Page 6 of 50

SI TERMINATION

'NP-

1 -ESP-

1.1

Step

Action/Expected Response

Response NOT Obtained -

Revision 17

8.10 Establish power to

1A 600 V LC emergency section

loads.

8.10.1 Verify pressurizer heater

group 1A - OFF.

8.10.2 Verify open BKR EA08-1.

8.10.3 Verify closed BKRs ED08-1

and EA09-1.

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

CAUTION: To prevent diesel generator overloading, at least 0.3 MW of diesel

generator capacity must he available prior to energizing a group of

pressurizer heaters.

NOTE :

The BYPASS position allows manual energization of pressurizer heater

group 1A from the MCB handswitch, and automatic energization based on

either pressurizer pressure 5 2210 psig or pressurizer level 5% above

program.

8.10.4 WHEN pressurizer heater

group 1A operation is

desired,

THEN place HTR GRP 1A

BLOCKING BYPASS SW to

BYPASS.

8.10.5 a

required,

THEN manually energize

pressurizer heater group

1A.

Step 8 continued on next page.

-Page Completed

Page 7 of 50

'NP-1-ESP-1.1

CAUTION: To ensure adequate supply voltage to all class 1E loads and to meet

short circuit analysis constraints, only one air compressor, 1C

(preferred) or 1A. should be powered from the diesel generator. One

air compressor will consume 0.16 MW of diesel generator load.

.

SI TERMINATION

Revision 17

8 . 1 1

Verify 1C air compressor in

8.11 Align 1A air compressor for

service.

service as follows.

8 . 1 1 . 1

Verify 1C air compressor

handswitch in RUN/START.

8 . 1 1 . 2

Verify 1C air compressor

started.

a) Verify 1C air compressor

handswitch in OFF.

b ) Verify SI - RESET.

[I MLB-1 1-1 not lit

[1 MLB-1 11-1 not lit

CAUTION: a

offsite power is lost after sequencer is.reset.

THEN manual actions may be required to restart safeguards equipment.

c) Reset B1F sequencer by

depressing the ESS STOP

RESET pushbutton on the

sequencer panel.

(139 ft, AUX BLDG A train

SWGR room)

d) Place BKR DF13 SYNCH

SWITCH in MAN.

e) Close BKR DF13 (1F 4160 V

bus tie to 1H 4160 V

bus) .

f)

1H 4160 V bus

energized.

THEN energize 1G 600 V LC

from normal supply.

[I BKR DHOl closed

[I BKR EG02-1 closed

Step 8 continued on next page

Paee Comoleted

_____

Page 8 of 50

FNP-1-ESP-1.1

8.12.1 Restore air pressure.

Verify proper air

compressor operation

using FNP-1-SOP-31.0.

COMPRESSED AIR SYSTEM.

I

-

OR

.IJ

2C air compressor

available,

THEN align 2C air

comuressor to Unit 1

SI TERMINATION

Revision 17

usiAg FNP- 1 -SOP-31.0.

COMPRESSED AIR SYSTEM.

8.12.2 a

instrument air NOT

restored,

-

THEN align nitrogen supply

to PORVs using

FNP-1-SOP-62.1. BACK-UP

AIR OR NITROGEN SUPPLY TO

THE PRESSURIZER POWER

OPERATED RELIEF VALVES.

8.12.3 a

instrument air NOT

restored,

THEN align emergency air

supply to atmospheric

relief valves and/or

TDAFWP using

FNP-1-SOP-62.0, EMERGENCY

AIR SYSTEM.

Step 8 continued on next page.

I-PaRe

Completed

Page 9 of 50

FNP-1-ESP-1.1

I

Step

ActiodExpected Response

Response NOT Obtained

I

SI TERMINATION

Revision 17

8.12.4

instrument air NOT

restored because 1G 600 V

LC is deenergized.

THEN energize 1G 600 V LC

from 1F 600 V LC using

FNP-1-SOP-36.3,

600,

480 AND 208/120 VOLT AC

ELECTRICAL DISTRIBUTION

SYSTEM.

8.12.5 WHEN instrument air

pressure restored.

THEN perform step 8.13.

8.12.6 Proceed to step 9.

-Page

Comuleted

8.13 Align instrument air to

containment. (BOP)

IA TO PENE RM

[ I NlP19HV3825 open

[I NlP19HV3885 open

IA TO CTMT

[I QlP19HV3611 open

Page 10 of 50

Step

ActiodExpected Response

Response NOT Obtained

CHG PUMPS TO

REGENERATIVE HX

[1 QlE21MOV8107 open

[I QlE21MOV8108 open

Step 9 continued on next page.

-Page

Completed

I

9

Isolate HHSI flow.

9.1 Check CHG PUMP - SUCTION

9.1 E CHG pump suction aligned to

ALIGNED TO RWST

RWST

recirculation mode,

TO CHG PMP

discharge of RHR Pumps [via

QlEllMOV8706A(B)I in the

THEN perform the following.

[I Q1E21LCV115B open

[1 QIE21LCV115D open

I

9.1.1 Manually close charging

flow control valve.

CHG FLOW

[1 FK 122

9.1.2

train A charging pump

running,

THEN perform the following.

IF NOT,

THEN proceed to RNO

Step 9.1.3.

-

Step n

Actionhxpected Response

Response NOT Obtained

- -

9.1.2.3

Verify only one charging

l i n e valve - OPEN.

RCS NORMAL

CHG LINE

[I QlE21HV8146

RCS ALT

CHG LINE

[I QlE21HV8147

9.1.2.4

Open charging flow

control valve FK-122 as

necessary t o obtain

54-58 gpm.

CHG FLOW

[J FK 122 manually adjusted

9.1.2.5

Close HHSI i s o l a t i o n

valves.

HHSl TO

RCS CL IS0

[1 QlEZlMOV8803A

[I QlE21MOV8803B

9.1.2.6

Verify charging flow

greater than 60 gpm.

9.1.2.7

Proceed t o Step 11.

S t e p 9 continued on next page.

-Page

Completed

Page 1 2 of SO

NP-1-ESP-1.1

SI TERMINATION

Step

n

Revision 17

Action/Expected Response

Response NOT Obtained

-

I

9.1.3 x t r a i n B charging pump

running,

-

THEN perform the following

9.1.3.1 Close HHSI isolation

valves.

HHSI TO

RCS CL IS0

[I QlE21MOV8803A

[I QlE21MOV8803B

9.1.3.2 Verify charging pump

discharge flow path -

ALIGNED.

CHG PUMP

DISCH HDR IS0

[I QlE21MOV8132A open

11 QlE21MOV8132B open

[I QlE21MOV8133A open

[I QlE21MOV8133B open

CHG PUMPS TO

REGENERATIVE HX

[] QlE21MOV8107 open

[I QlE21MOV8108 open

9.1.3.3 Verify only one charging

line valve - OPEN.

RCS NORMAL

CHG LINE

[I QlE21HV8146

RCS ALT

CHG LINE

[I QlE21HV8147

9.1.3.4 Open charging flow

control valve FK-122 as

necessary to obtain

54-58 gpm.

CHG FLOW

[I FK 122 manually adjusted

Step 9 continued on next page.

-

Page Completed

Page 13 of 50

Revision 17

I

NP-1-ESP-1.1

SI TERMINATION

Step

n

9 .

Action/Expected Response

Response NOT Obtained

Verify charging pump mini

valves - OPEN.

lA(lB.1C) CHG PUMP

MINIFLOW IS0

[I QlE21MOV8109A

[I QlE21MOV8109B

[ I QlE21MOV8109C

CHG PUMP

MINIFLOW IS0

[ I QlE21MOV8106

I

9.1.3.5 Close charging pump

recirculation to RCS

cold legs valve.

CHG PUMP RECIRC

TO RCS COLD LEGS

[I QlE21MOV8885

9.1.3.6 Verify charging flow

greater than 60 gpm.

9.1.3.7 Proceed to Step 11.

ow

9.3 Close HHSI isolation valves

HHSI TO

RCS CL IS0

[ I QlE21MOV8803A

[I QlE21MOV8803B

-Page

Completed

Page 14 of 50

S I TERMINATION

IP-1-ESP-1.1

Step

Actionhxpected Response

r

-

i

y

10

Establish normal charging.

10.1 Manually close charging flow

control valve.

CHG FLOW

[ ] EK 122

1 0 . 2

Verify charging flow path

aligned.

Revision 17

Response NOT Obtained

1

10.2.1

I

Verify charging pump

discharge flow path

ALIGNED.

(;IC PUMP

I!ISCII HDR IS0

(; I I:% 1 MOV8132A open

(:II:%lMOV8132B open

cril:%1MOV8133A open

(;II:7.1MOV8133B open

!:iic:

I'UMI'S TO

I:!:i:I:NI.RATIVE

HX

I I (:II:%IMOV8107 open

1 I (!l1;71MOV8108 open

1 0 . 2 . 7

V i , r i f y o n l y one charging

I iiir v a l v e - OPEN.

llCS NOKMAL

CIK; LINE

j I 011:2111V8146

IKS ALT

CllG LINE

[ I 01121HV8147

Step 10 continued on next page.

-

Page Completed

Page 15 of 50

NP-1-ESP-1.1

S I TERMINATION

Step

ActionlExpected Response

Response NOT Obtained

3

Revision 1 7

NOTE:

The RCS may be approaching s o l i d p l a n t c o n d i t i o n s .

RCS must be operated w a t e r s o l i d . c h a r g i n g flow should be adjusted t o

maintain subcooling i n s t e a d of p r e s s u r i z e r l e v e l .

I n t h e event t h e

11

-

1 0 . 2 . 3 Esta

main

15%-50%(48%-52%1.

10.2.3.1

Control charging flow.

CHG FLOW

I] FK 122 a d j u s t e d

Secure RHR system.

1 0 . 2 . 3

Perform t h e following.

nnot be maintained

greater than 15%148%1.

perform the

owing.

1) E s t a b l i s h HHSI flow

u s i n g ATTACHMENT 2.

FLOW

RE-ESTABLISHING HHSI

> ) GO t o FNP-1-ESP-1.2,

POST LOCA COOLDOWN

AND DEPRESSURIZATION.

-

I F s o l i d plant operation

r e q u i r e d .

THEN c o n t r o l charging

flow t o maintain

subcooling greater than

16"F[45"F].

CHG FLOW

-

[I FK 122 adlusted

11.1 Stop both RHR PUMPS.

11.2 Isolate CCW t o the on s e r v i c e

t r a i n RHR heat exchanger.

ccw TO

l A ( 1 B ) RHR HX

[I QlP17MOV3185A closed

[I QlPlizV3185B closed

OR

-

Page Completed

Page 16 o f 50

FNP-1-ESP-1.1

SI TERMINATION

12.2 Check pressurizer level -

GREATER THAN 7%(50%1.

Revision 17

12.2 Perform the following.

12.2.1 Establish HHSI flow using

ATTACHMENT 2,

RE-ESTABLISHING HHSI FAOW

12.2.2 GO to FNP-1 EEP-1, LOSS OF

REACTOR OR SECONDARY

COOLANT.

-

13

Check containment spray system.

13.1 Check any CS PUMP - STARTED.

13.1 Proceed to step 14

13.2 Reset containment spray

signals.

CS RESET

[I A TRN

[I B TRN

13.3 WHEN containment spray

recirculation flow has been

aligned for at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

-

AND containment pressure is

less than 16 psig,

-

THEN stop both CS PUMPS.

-

Page Completed

Page 17 of 50

81. 026A2.07 001/2/I//CIA 3.6/3.9/NIFA03301ISISDR

Unit 1 was at 100% power when a Large Break LOCA occurred inside containment. The

crew has responded per the ERGS and has transitioned to ESP-I .3, Transfer to Cold

Leg Recirculation, from EEP-1, Loss of Reactor or Secondary Coolant, Step 16. While

aligning 1 B RHR pump for cold leg recirculation, Containment pressure reached 27

psig. Both trains of containment spray have actuated.

The crew is currently performing Step 8 of ESP-1.3 checking containment spray in

operation. RWST level is 4.4 ft and slowly decreasing.

Which ONE of the following discribes the correct actions and procedure transition, if

any, required to mitigate this condition?

A. Secure the CS pumps, then transition to FRP-Z.1, Response to High Containment

Pressure.

B. Align the CS pumps for cold leg recirculation, then transition to FRP-Z.l, Response

to High Containment Pressure.

C. Transition to ECP-1.1, Loss of Emergency Recirculation.

D. Continue in ESP-I .3 and subsequently return to the procedure and step in effect (Le.

EEP-1, step 16)

NEED Licensee to verify that answer 'A' is the expected response. The information

provided to the NRC for exam development did not address this situation.

LICENSEE VALIDATION IS REQUIRED.

A - Correct; An ORANGE path exist for containment pressure.

B - Incorrect; NEED Licensee to veriv that this is not an expected response for this

condition otherwise a new distracter needs to be developed.

C - Incorrect; this is a logical procedure to transition to although not supported in step 9

of ESP-I .3. ESP-I .3 has no RNO actions for this situation. Lesson plan OPS-52531G

page 10, states that if at least one path from the sump to the RCS cannot be

established a transition to ECP-1.1 is made. The lesson plan does not address if a path

from the sump to the containment spray can not be established.

D - Incorrect; to continue in ESP-I .3 would result in securing all supply to the running

containment spray pumps without instructions to secure the pumps.

Change question to accept A and B

The stem of the question ask which ONE of the following (A, B, C, D) describes the

correct actions and procedure transition, if any, required to mitigate this condition.

A.

Secure the CS pumps, then transition to FRP-Z.1, Response to High

Containment Pressure.

This is designated as the correct answer, and is a proper response and

procedure transition. An ORANGE path exists for containment pressure and due to the

Continuing action step of ESP-I .3 and being 4.5 in the RWST, IF it is determined that

swap over is NOT imminent the CS pumps are secured, and a transition made to FRP-

z.1.

However, B actions could be acceptable in the described situation making B a possible

correct answer.

B

Align the CS pumps for cold leg recirculation, then transition to FRP-Z.l,

Response to High Containment Pressure.

This is the most conservative answer and correct depending on how the word

then is interpreted. A Shift Supervisor with knowledge of the requirements of FRP-Z-1

would likely direct an Operator to place the CS pumps on cold leg recirculation while

transitioning to FRP-Z.1. The SS realizes that FRP-Z-1 will place the pumps on

recirculation in step 3.4. In this case the actions of FRP-Z-1 and ESP-1.3 for aligning

containment spray for recirculation coincide, would be taking place regardless and the

entry to FRP-Z.l would not be delayed. At our plant we often start one step with the

UOlOATC and then the team will continue on while that step is being completed. The

word then is often utilized to give continuing action once a step has been

implemented, i.e. to start aligning the CS pumps recirculation off of the containment

sump while transitioning to FRP-Z-1 .

This is actuallv the most conservative thing to do since containment pressure is

rising and both ESP-I .3 and FRP-Z.l have you place CS on recirculation. If the CS

pumps just started as the stem maintains, then the CS pumps would be stopped in

answer A

response and then restarted within a few minutes. Hot starts on the pumps

and repeated cycling of breakers pose additional threats to accident recovery and

should not be performed unnecessarily. The conservative thing to do utilizing Operator

knowledge of upcoming procedural actions would be to leave the pumps running, use

an operator to complete the swap-over to help maintain the integrity of containment

while the team continues on to FRP-Z.1. The procedure for aligning containment spray

for recirculation does not require that the pumps be stopped. The containment sump

suctions are opened before the RWST suctions are closed. Therefore answer B actions

would be acceptable in the described situation.

Also when step 8 of the procedure is reached, FRP-Z.l is entered only after an

evaluation that there are no red paths or higher priority orange paths. During the

performance of this evaluation (typically done by the STA) the crew would be

proceeding. Per the stem (both trains of containment spray have actuated), Step 8

would be completed by observing the pump hand switches before the evaluation was

completed and the crew would be at step 9.

8

9

Check containment spray - IN OPERATION.

WHEN RWST level less than 4.5 ft,

THEN align containment spray for

cold leg recirculation.

Also in this case the rules of usage state (SOP-0.8):

3.8

Continuous Actions

Certain operator actions provided in a procedure direct or imply continuous

performance throughout the remainder of the procedure. A continuous action is an

action that is applicable from the point at which it is first encountered until superseded

by alternate guidance or stated to be inapplicable. A continuous action generally

remains applicable throughout its associated procedure unless otherwise stated, and

may apply after a transition is made to another procedure if it does not contain any

actions that are inappropriate for the subsequent procedure.

Tripping the containment spray pumps with 27 psig in containment could be

evaluated as inappropriate.

Since step 9 is a continuing action step the above rules of usage states the crew

should evaluate if it is appropriate to continue alignment for recirculation while in FRP-

Z. 1. This evaluation could determine that tripping the pumps is inappropriate because

recirculation is imminent.

Answer C is incorrect based on the information provided for this distracter.

Answer D is incorrect because a transition to FRP-Z.l is required for the existing

conditions.

01/09/03 11:35:58

FNP-0-SOP-0.8

Notes or caution statements are placed just prior to the step to which they apply.

If a note or caution step applies to a sequence of steps, it is placed just prior to the

first step in the sequence. Any note or caution statement which applies to an

entire procedure is placed prior to the first operator action step.

Since notes and caution statements provide information needed to support proper

performance of the operator action steps, each note or caution statement must be

read and understood prior to performing the applicable steps. When the user is

directed to a specific ERF' step, he must always read and understand any notes or

caution statements applicable to that step.

3.3

Terms and Action Verbs

To ensure correct performance, directed action verbs used in the ERPs are

restricted to a specific defined set. These verbs and other special terms are

presented in Attachment 1.

3.4

Step Performance

The operator action steps are arranged in a two column format. The left column

is the Action/Expected Response (AER) column. The right column is the

Response NOT Obtained (RNO) column. The expected operator actions are

presented in the A/ER column in the order of performance. If the step cannot be

pcrfornied or the specified condition is not met, the user shall go to the RNO

colunin for that step and take the action(s) described. After the action steps in the

RNO column have been performed or if they cannot be performed, the user

should return to the AER column for the next action step. The user should keep

in mind any actions which could not be performed and complete them later as

appropriate.

The operator action steps in both the A E R and RNO columns are normally

required to be performed sequentially in the numerical order specified. High

level action steps will always be numbered. If the order of performance of a

group of high level action steps is not important, this would be specifically stated

in a note prior to the first step in the group. Substeps will be numbered if the

order of performance is important. If the substeps may be performed in any order,

the substep will have a bullet ( 0 ) instead of a number.

If two steps should be performed simultaneously instead of

sequentially, a note or caution statement is placed prior to the first step to alert the

user.

-3-

Version 7.0

01/09/03 11:35:58

FNP-0-SOP-0.8

Following verification of immediate actions, the Shift Supervisor will proceed

expeditiously to implement subsequent actions. If the UO is not in the Control

Room when an event occurs, performance of the immediate actions by the OATC

alone is sufficient. Concurrent with starting subsequent actions, the shift

supervisor should ensure the UO or another licensed operator responds to assist in

the implementation of the ERP.

3.8

Continuous Actions (CMT0008169)

Certain operator actions provided in a procedure direct or imply continuous

performance throughout the remainder of the procedure. A continuous action is an

action that is applicable from the point at which it is first encountered until

superseded by alternate guidance or stated to be inapplicable. A continuous action