ML032340714

__ Compare MlP1385 (U1 Reactor Thermal Power, Best) to

Control Board Power Range gauges.

-

NOTE: surveillance of Power Range/Heat Balance (Thermal Power) performed prior to

normal surveillance time period, surveillance must be performed an additional time to

return surveillance period to normal surveillance period of 0100-0700.

12.16.2.4 Ensure Reactor Powermeat Balance (Thermal Power)

surveillance is performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from Datemime

surveillance was performed in Step 12.16.2.2 for which PI data

was used.

12.16.2.5 Ensure Power Rangemeat Balance (Thermal Power) logged on

Conditional Surveillance Board until returned to normal

surveillance period with OAC operable.

Unit 1

PT/1/N4600/021 A

Page 16 of 17

__ 12.16.3 valid PI data is unavailable, notify Reactor Group Engineer or designee to

perform PT/O/N4150/039 (Manual Calculation of Thermal Power).

Person Contacted Date Time

-- I

Calculation Performed By Date Time

12.17 WHEN OAC returned to service, update and check the following:

0 XenonData

0 Burnup

0 Thermal Outputs

0 100% Target AFD Values

__ 12.17.1 Notify Reactor Group Duty Engineer values have been updated.

Person Contacted Date Time

12.18 WHEN OAC is returned to service, notify RP Shift that PI data collection is available.

1

--

Person Contacted Date Time

Unit 1

PT/1/A/4600/021 A

Page 17 of 17

1

>~ I

d\

13. Enclosures

13.1 Hourly Dispatcher Report

13.2 Axial Flux Difference Monitoring

13.3 Full Length Rod Verification Data

13.4 Containment Air Temperatures

13.5 Calculation Sheet For Quadrant Power Tilt

13.6 FWST Level Instrument Room Temperature

13.7 OAC Point List For Partial Loss Of OAC

13.8 CA Storage Tank Temperatures

13.9 Manual Trigger of Analog Fault Recorder

..---... .

. EndofBody

Unit 1

Time ' PR-41 PR-42 PR-43 PR-44

Initials A B A B A B A B

1) Measured Current

~ ~

2) Calibration Current

3) Relative Flux (RF)

1) From NI cabinet's current meter (located on respective PR B Drawers). Ensure Detector Milliamp Range Switches

are in "0.5" position and read 0-500 microamp scale.

2) From most recent calibration data using " 0Incore Axial Offset Current in Data Book, Table 2.2 ("IFfor detector

" A , "IB" for detector "B").

3) Divide line 1 by line 2 to calculate Relative Flux (RF) for each upper (A) and lower (B) detector.

Ouadrant Power Tilts: Calculate by dividing each upper relative flux by the average upper relative

flux and dividing each lower relative flux by the average lower relative flux

-.

~

Avg RF of A Detectors =

@FA)

IRF of P R 4 1 A

+I ]

RF of PR-42A

+ (

RF of P R 4 3 A

+T

RF of PR-44A

I x Yi =

d-

Avg RF of B Detectors =

(RFW RF of PR-41B

+ I R F of PR-42B

+ TRF of PR-43B I + T RF of P R 4 B

Ix % =

PR-41A Tilt = RF of PR-41A = PR-41B Tilt = RF of PR-41B =

RFA RFB

-~

PR-42A Tilt = RF of PR-42A = PR-42B Tilt = RF of PR-42B =

RFA RFB

PR-43A Tilt = RF of PR-43A = PR-43B Tilt = RF of PR-43B =

RFA RFB

PR-44A Tilt = RF of PR-44A = PR-44B Tilt = RF of PR-44B =

RFA RFB

' above 50% RTP, calculation performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter until QPTR Alarm

operable.

Unit 1

Time * PR-4- PR-4-

~ _ _ _ _PR-4-_ _ _

Initials A B A B A B

1) Measured Current

2) Calibration Current

I 3) Relative Flux (RF) I I I I

1) From NI cabinet's current meter (located on respective PR B Drawers). Ensure Detector Milliamp Range Switches

are in "0.5" position and read 0-500microamp scale.

2) From most recent calibration data using "0" Incore Axial Offset Current in Data Book, Table 2.2 (1; for detector

" A , "I; for detector "B").

3) Divide line 1 by line 2 to calculate Relative Flux (RF)for each upper (A) and lower (B) detector.

Ouadrant Power Tilts: Calculate by dividing each upper relative flux by the average upper relative

flux and dividing each lower relative flux by the average lower relative flux

Avg RF of A Detectors =

@FA)

T I

RF of PR-

+

RF of PR-

+ F i x

RF of PR-

% =

4-A 4-A 4-A

.

-."

., Avg RF of B Detectors = -+

(RFB) RF of PR-4-B RF of PR-4-B

nX%=

RF of PR-4-B

PR-4-A Tilt = RF of PR-4 A = PR-4-B Tilt = RF of PR-4 B =

RFA RFB

PR-4-A Tilt = RF of PR-4 A = PR-4-B Tilt = RF of PR-4 B =

RFA RFB

PR-4-A Tilt = RF of PR-4 A = PR-4-B Tilt = RF of PR-4 B =

RFA RFB

End of Enclosure

WHEN greater than 50% RTP hut less than 75% RTP, calculation performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

thereafter while QPTR Alarm inoperable one PR channel input inoperable.

Unit 1

RO/SRO Admin A-1b JPM

PAGE 1 OF 4

Reviewed By

Approved By

TASK: Calculate the Boric Acid Change for a specified Rod Change

POSITION: ROlSRO

Operator's Name

Validation Time: 20 minutes

Location: Simulator/Plant Method: Perform

The JPM Operator's performance was evaluated against the standards of this JPM and

is determined to be:

SATISFACTORYIUNSATISFACTORY (circle one)

Evaluator's Signature Date I I

References: 0P111A/6100122 (Rev. 476) Unit 1 Data Book

JPM verified current with references by

Date I I

Rev. 01/03-31-03

ROlSRO Admin A-I b JPM

PAGE 2 OF 4

INITIAL CONDITIONS

The following conditions exist:

Unit 1 Reactor Power is at 90% with Xe at equilibrium conditions

Core burnup is 350 EFPD

NC Boron Concentration = 1020 PPM

Present Control Rods Bank D at 195 steps

Desired Rod Height is Control Rods Bank D at 160 steps

The Control Room SRO directs you to calculate the Desired NC Boron

Concentration and the Boric Acid Change required for the change in rod position

(utilizing the Data Book) while maintaining the present power level.

JPM OVERALL STANDARD: Primary water addition of approximately 1334

gallons is calculated within 2 150 gallons.

NOTES: Unit 1 Data Book should be available for reference.

ROlSRO Admin A-1 b JPM

PAGE 3 OF 4

START TIME

-

STEPS ELEMENTS STANDARD SIU COMMENTS

REQUIRED

FOR UNSAT

I Operator determines Initial inserted reactivity

195 steps integral rod worth =

worth using the 350 84 pcm

EFPD column of Table

6.3.3 HFP, Equilibrium

Xe

2 Operator determines Desired Rod height

160 steps integral rod inserted reactivity worth

worth using the 350 -

EFPD column of Table 224 pcm

6.3.3 HFP, Equilibrium

Xe

i/

._.

3 Operator determines Change in reactivity to

the change in reactivity be compensated to rod

required for the rod withdrawal =

insertion + 140 pcm

4 Using Graph 6.8 Operator determines the

Differential Boron Differential Boron Worth

Worth, determines the from the graph to be =

Differential Boron -7.28 pcmlppm

Worth for present

conditions

5 Using the Differential Operator determines the

Boron Worth and the change in Boron

Change in reactivity, Concentration to be =

determines the change +I40 I-7.28 pcmlppm

in Boron Concentration

of NCS. = -19.23ppm

uv

DENOTES CRITICAL

ROlSRO Admin A-I b JPM

PAGE 4 OF 4

STEPS ELEMENTS SIU COMMENTS

REQUIRED

FOR UNSAT

-

Operator determines Change in Boron =

Boron Concentration 1020 - 19.23 ppm

change required

= 1000.77 pDm

-

7 Using Enclosure 4.3 Using Present Boron

Section 5.1 Boron and Conc 1020 ppm and the

Dilution Tables, Desired Boron Conc of

determines the primary 1000.77 ppm,

water addition determines the primary

water addition =

-1 334 qallons

(+ or - 150 qallons)

I------Operator determines

an addition of Primary

water is necessary.

.

'Cue:

The SRO has directed

1 another operator to

complete the Boric

Acid change.

STOP TIME

u

.. ,

DENOTES CRITICAL

\'

L'

INITIAL CONDITIONS

The following conditions exist:

Unit 1 Reactor Power is at 90% with Xe at equilibrium conditions

Core burnup is 350 EFPD

NC Boron Concentration = 1020 PPM

Present Control Rods Bank "D" at 195 steps

Desired Rod Height is Control Rods Bank "D" at 160 steps

The Control Room SRO directs you to calculate the Desired NC Boron

Concentration and the Boric Acid Chanqe required for the change in rod position

(utilizing the Data Book) while maintaining the present power level.

RO Admin A-2 JPM

PAGE 1 OF 4

\

Reviewed By

L;'

Approved By

TASK: Initiate a Tagout

POSITION: USRO

Operator's Name

Location: Control Room Method: Perform

L The JPM Operator's performance was evaluated against the standards of this JPM and is

determined to be:

SAT1SFACTORYIUNSAT1SFACTORY (circle one)

Evaluator's Signature Date I 1

.

~~

References: MC-1554-03.00 Flow Diagram of NV System

KA 194 001 K102

Attachments:

Rev. 01103-18-03

RO Admin A-2 JPM

PAGE2OF 4

\

L

INITIAL CONDITIONS

Unit 1 is operating at 100% power

There is no PRE-PLAN available on the Red Tag Computer.

1NV-803 (PDP #I Outlet Isol) has been found in the CLOSED position. In an attempt to correct

this mispo, the OSM directed an operator to open the valve. When attempt to open the valve

began, the valve stem broke off completely (valve still fully closed). Maintenancewas notified

and requested the valve be tagged out in order to mark on the valve internals, as well as, the

stem replacement.

You have been directed to generate a sequenced list to be used for development of a

tagout to allow Maintenance to disassemble the valve and work on the valve

internalslcomponents.

JPM OVERALL STANDARD: The list is generated with technical correctness.

NOTES: The operator should be given the associated flow diagram.

KA 194 001 K102

RO Admin A-2 JPM

PAGE3OF 4

STEPS ELEMENTS STANDARD s/u COMMENT:

REQUIRED

FOR UNSAT

I 2omponent verified to be Component verified

ompletely isolated isolated per attached flow

diagram

2 solation valves, pump Same

lower supply, vents and

lrains are identified as

ioundaries

3 Sequence correctly Pump is sequenced to be

dentified: electrically tagged prior to

the hydraulic tagout.

Hydraulic tagout

3PEN boundaries are

sequenced closed prior to

PDP power supply vents/drains being

OPTIONAL: sequenced open.

Suction Dampener

Heater Breaker

NOTE: As long as the

XOSE pump breaker is racked

INV-219 out first, the isolation

valves can be aligned in

INV-217 any sequence.

INV-2780~

I

1NV-279

INV-839

INV-1048~

1NV-1047 &

supply breaker

u * DENOTES CRITICAL

RO Admin A-2 JPM

PAGE 4 OF 4

STEPS ELEMENTS STANDARD s/u COMMENT:

REQUIRED

FOR UNSAT

"3 3PEN One vent or drain is

required to be tagged

1NV-834& open on each side of the

1NV-1050 valve to be worked.

1NV-270& OR:

INV-271 Or Some contingency plan

1NV-272 must be in place on how

1NV-273 to venffdrain both sides of

the valve.

OPTIONAL OPEN:

INV-830

NOTE: For more info,

or Refer to OMP 7-1

INV-272 &

1NV-278

OPTIONAL LISTING:

1NV-803 placed on VAR

\I

DENOTES CRITICAL

INITIAL CONDITIONS

Unit 1 is operating at 100% power.

There is no PRE-PLAN available on the Red Tag Computer.

1NV-803 (PDP #I Outlet Isol) has been found in the CLOSED position. In an attempt to correct

this mispo, the OSM directed an operator to open the valve. When attempt to open the valve

began, the valve stem broke off completely (valve still fully closed). Maintenance was notified

and requested the valve be tagged out in order to work on the valve internals, as well as, the

stem replacement.

You have been directed to generate a sequenced list to be used for development of a

tagout to allow Maintenance to disassemble the valve and work on the valve

internalslcomponents.

06/11/03 WED 07:06 FAX 704 8 7 5 5 0 9 4 HLP EXAM DEV @003

RO Admin A-3 JPM

PAGE I OF 3

TASk? Utilizing a Survey Map, calculate the maximum permissible Stay Time

within the ALERT limit of the Duke Power Basic Administrative limits.

POSITION: RO

-

Operator's Name

Localion: Control Room Method: Perform

--' The .IPM Operatoor's performancewas evaluated against the standards of this JPM and is

determined to be:

SATlSFACTORY/UNSATlSFACTORY (circle one)

Evaluator's Signature Date I I

Refeisnces: Duke Power Company, Radiation Worker Training Student Guide

Atkc hments:

Rev. 01106-10-03

06/11/03 WED 07:06 FAX 704 8 7 5 5094 HLP EXAH DEV

@I004

RO Admin A-3 JPM

PAGE 2 OF 3

-

b-., INITIAL CONDITIONS

A SGTR in conjunction with a LOCA has occurred. Due to previous amounts of failed fuel, the

radia.ion levels in the Auxiliary Building are abnormally high.

An individual has been assigned the task of performing a valve lineup in the NM Lab (see

attached Survey Map). Assume that all areas in the room must be accessed, but valves on the

S/G Ines are the only required manipulations.

The individual has previously received 1145 mrem total dose this year.

Determine the maximum permissible time an individual can work in the area without

violating the ALERT. limit of the Duke Power Basic Administrative limit.

JPM OVERALL STANDARD:

Stay Time is correctly calculated and the Duke Power Basic Administrative limit is not violated.

ii

NOTES:

DPC Admin limit: 2000 mrem X 80% = ALERT Admin limit

ALERT Admin limit: 1600 mrem

Dose history -1145 mrem

Max mum Permissible dose: 455 mrem

Maximum Stay Time: 455 mrem / 160 rnredhr 3 2.84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months or less

ACCEPTABLE RANGE: 2.80 to 2.85 hours9.837963e-4 days 0.0236 hours 1.405423e-4 weeks 3.23425e-5 months or less

06/11/03 WED 07:06 FAX 704 a75 5094 BLP EXAX DEV

RO Admin A-3 JPM

PAGE 3 OF 3

STEiPS ELEMENTS STANDARD COMMENT:

REQUIRED

-- FOR UNSAT

I Determines the remaining Permissible dose is

permissible dose within determined to be:

the DPC Basic limit.

455 mrem

--

2 Determines the maximum Maximum Stay Time is

permissible Stay Time determined to be:

within the DPC Basic

el= 2.80 to 2.85 hours9.837963e-4 days 0.0236 hours 1.405423e-4 weeks 3.23425e-5 months

limit.

_.-

-..'

u * DENOTES CRITICAL

08/11/03 WED 07:OE FAX 7 0 4 875 5 0 9 4 BLP EXAE DEV moo6

~

INITIAL CONDITIONS

A SGTR in conjunction with a LOCA has occurred. Due to previous amounts of failed fuel, the

radiaiion levels in the Auxiliary Building are abnormally high.

An individual has been assigned the task of performing a valve lineup in the NM Lab (see

attamed Survey Map). Assume that all areas in the room must be accessed, but valves on the

S/G lines are the only required manipulations.

The individual has previously received 1145 mrem total dose this year.

Determine the maximum permissible time an individual can work in the area without

violating the ALERT limit of the Duke Power Basic Administrative limit.

06/11/03 WED 07:06 FAX 7 0 4 875 5 0 9 4 BLP EXAM DEV a007

McGuire Nuclear Station

Radiological Plan View

Date: [f%ESEU)

-,

e-...,, Location: Unit-1 NM Lab

Surveyed by: P 7ech

-

CONTAMINATED AREA

Dress Out Required

h I I

A'

2

'OU ARE HERE

A

'Radiation readings in mremlhour u n l c ~ rotherwise naled

'"Contaminated Arm" indicatcs the rwm/arca i s greatcr than

IMXldpd100cmZ

RO Admin A-3 JPM

PAGE 1 OF 6

TASK: Determine Requirements for Reactor Building Entry

POSITION: RO

Operator's Name

Location: PlantlSimulator Method: Perform

Estimated JPM Completion Time: 1 0Minutes

Actual JPM Completion Time: Minutes

The JPM Operator's performance was evaluated against the standards of this JPM and is

determined to be:

i;I:

SATISFACTORYIUNSATISFACTORY (circle one)

Evaluator's Signature Date I I

-.

References: RWP #26

JPM verified current with references by

Date I 1

Rev. 04103-31-03

RO Admin A-3 JPM

PAGE 2 OF 6

\

L

INITIAL CONDITIONS

Unit 1 is in Mode 1.

You have been directed to enter the Reactor Building Pipe Chase and perform a general

inspection. Entry will be governed under the provisions of RWP #26. Determine the

requirements of this RWP for a work in dry contaminated areas to perform light work.

JPM OVERALL STANDARD: Operator determines the proper Dress requirements,

Dosimetry requirements, Respiratory requirements, Dose

Alarm setpoint, Dose Rate Alarm setpoint, any Special

requirements.

NOTES: The examinee must be provided a copy of RWP #26 and RWP Dress Category

u Codes.

RO Admin A-3 JPM

PAGE 3 OF 6

START TIME

-

STEPS ELEMENTS STANDARD SIU COMMENT!

REQUIRED

FOR UNSAT

Cue:

Determine the required

protective clothing

necessary to perform

work under this RWP as

a "G" w orker

"1 letermine the required Operator determines the

xotective clothing for following protective

3WP #26 G worker clothing required:

Cloth hood, disposable

coveralls, cotton and

rubber gloves, booties

and shoecovers.

(secured with tape)

Cue:

Determine the expected

dose rates.

"2 Determine expected Operator determines

dose rates using RWP that expected dose

26 rates 1 mremlhr -->

2000 mrem/hr.

%,

DENOTES CRITICAL

RO Admin A-3 JPM

PAGE 4 OF 6

STEPS ELEMENTS STANDARD s/u COMMENT!

REQUIRED

FOR UNSAT

-

Cue:

Determine the

Respiratory

requirements for this

RWP

3 Determines that RP Operator determines

must be notified t o that RP must be notified

determine if respiratory to determine if

requirements based on respiratory requirements

TEDE/ALARA evaluation based on TEDE/ALARA

using RWP #26 evaluation

Cue:

Determine the Dose

Alarm setpoint and the

Dose Rate Alarm

setpoint in effect for

this RWP

~~

4 Determine the Dose Operator determines the

Alarm and Dose Rate following setpoints:

Alarm setpoints for RWP Dose Alarm: 25 MREM

26

Dose Rate Alarm:

100 MREMlHR

u

I_

RO Admin A-3 JPM

PAGE 5 OF 6

STEPS ELEMENTS STANDARD SIU COMMENT:

REQUIRED

FOR UNSAT

Cue:

Under what conditions

does RP need to be

notified?

5 Determine the times Operator determines

where RP needs to be that RP needs to be

notified per the notified prior to the start

requirements of RWP of work.

26.

Cue:

What, if any, Special

Instructions must be

met prior to entry

6 Determine

- the Special Operator determines

Instructions necessary that a Pre-Job Briefing is

prior to entry per RWP required prior to entry

26

Cue:

What, if any. areas

must be avoided during

entry?

il.

RO Admin A-3 JPM

PAGE 6 OF 6

~ ~

STEPS ELEMENTS STANDARD COMMENT

REQUIRED

FOR UNSAT

7 Determine the areas to Operator determines

be avoided per RWP that Extra High

26 Radiation Areas

(designated by yellow

flashing lights) must not

be entered without RP

coverage.

Cue:

When is an Auxiliary ED

Alarm required?

8 Determine when Operator determines

Auxiliary ED Alarm is that an Auxiliary ED

required per RWP #26 Alarm is required if any

of the following

conditions exists:

Gen Area Rad

levels are

> 5 rnrem/hr

High noise level in

the work area

Useof headphone

Hearing impaired

Other conditions

that would impair

hearing the ED

alarm.

u STOP TIME

_,

DENOTES CRITICAL

INITIAL CONDITIONS

Unit 1 is in Mode 1.

You have been directed to enter the Reactor Building Pipe Chase and perform a general

inspection. Entry will be governed under the provisions of RWP #26. Determine the

requirements of this RWP for a work in dry contaminated areas to perform light work.

MCGUIRE NUCLEAR STATION

Worker Version

I2109102 13:18

Revision # :

Radiation Work Permit #: 26 13

Job Title: REACTOR BUILDING PIPE CHASE. A N D SEAL TABLE ENTRY DURING

POWER OPERATIONS MNSICNS ONLY

L\,

ED (MG) Set Points

Dose Alarm: 25 mrem Dose Rate Alarm: 100 mrem/hr

Dress Category, Task Description, Special Dosimetry and Respiratory Requirements

Dress Special

Category T a s k Description Dosimetry Respiratory

A WORKER IN A NON-CONTAMINATED AREA NONE NONE USED

B WORK WITH POTENTIALLY CONTAMINATED MAT. WHERE THERE I S A LOWPOTENTIAL FOR CONTACT WITH NONE NONE USED

MAT. OTHER THAN BY THE HAND.

E WORK ASSOCIATED WITH A CONTAMINATED SYS AND/OR CONTAMlNATEDlRAD MATL WHERE POTENTIAL NONE NONE USED

FOR PERSONNEL CONTAMINATION IS LOW.

G WORKER IN DRY CONTAMINATED AREAS TO PERFORM LIGHT WORK NONE NONE USED

H WORKER IN DRY CONTAMINATED AREA NONE NONE USED

K WORKER IN CONTAMINATED AREA WHERE ADDITIONAL CONTROLS ARE NEEDED OR HOT PARTICLES ARE NONE NONE USED

A CONCERN

WORKER IN DRY CONTAMINATED AREA WHERE HEAVY WORK IS PERFORMED AND ADDITIONAL NONE NONE USED

CONTROLS ARE NEEDED-RP APPROVAL REQ

N WORKER IN WET AREA (BOTTOMS ONLY WHEN CONCERNS ARE BELOW T I E WAIST) NONE NONE USED

Comments/Special Instructions

RESPIRATORY REQUIREMENTS W I L L B E BASED ON TEDE/ALARA

EVALUATION

EXPECTED DOSE RATES: I MREMIHR - - > ZUUU MREMIHR

AUXILIARY ED ALARM REQUIREMENT ONLY A P P L I E S I N AREAS

WHERE GENERAL AREA RADIATION LEVELS ARE GREATER THAN S

MREMIHR

N O T I F Y RP P R I O R T O START O F WORK

PRE-JOB B R I E F I N G REQUIRED

f DO NOT ENTER EXTRA HIGH RADIATION AREAS, DESIGNATED BY

YELLOW FLASHING L I G H T S WITHOUT R P COVERAGE

AN AUXILIARY ED ALARM I S REQUIRED I F ANY OF THE

FOLLOWING C O N D I T I O N S E X I S T : H I G H N O I S E LEVEL I N THE

WORK AREA, USE OF HEADPHONES, HEARING IMPAI9MENT. OR

4 N Y OTHER CONDITION THAT WOULD IMPAII? iiEARING THE ED

L . 8 '

~ ALARM

New Page Page 1 of 1

RWP Dress Category Codes

Dress Category Description

I

http://ngoweb/Ssd/rp/Dose-RWF'RWP-Dress-Codes.htm 3/31/2003

ES-301 Administrative Topics Outline Form ES-301-1

-

Facility: McGuire Date ofExamination: Weeks of June 16 and 23, 2003

Examination Level (circle one): RO / SRO Operating Test Number:

I Administrative Topic Describe activity to b e performed-

. .

I: Bess@m- {see Note)

A4 Evaluate Overtime Eligibility

I. Conduct of Operations (Modified)

L

Calculated Boron Change for Rod Change

Conduct of Operations (Modified, Common)

Evaluate a Work Order for Clearance to do Work,

(New)

Evaluate Liquid Waste Release with Fault

(New)

Evaluate Condition for PARS

(Alternate if General Emergency Not Declared)

I NOTE: All items (5 total) are required for SROs, RO applicants require only 4 items unless

thev are retakinq only the administrative toDics, when 5 are required.

22 of 27 NUREG 1021, Draff Revision 9

SRO Admin A-la JPM

PAGE 1 OF 3

TASK: Evaluate Overtime Eligibility

POSITION: SRO

Operator's Name

Location: Control Room Method: Perform

L3

The JPM Operator's performance was evaluated against the standards of this JPM and is

determined to be:

SAT1SFACTORYlUNSAT1SFACTORY (circle one)

Evaluator's Signature Date I I

References: NSD-200

KA 2.1.5

Rev. 0010335-03

SRO Admin A-la JPM

PAGE 2 OF 3

INITIAL CONDITIONS

Due to plant startup activities, an Reactor Operator must be held over for the following shift for

three (3) hours.

Evaluate the following five Reactor Operators for availability to work 3 more hours without

an Overtime Extension and determine if the hours worked has exceeded NSD-200

requirements. State requirements that are violated, if applicable.

The following is the work history (excluding shift turnover time) of the available Reactor Operators

on shift (hours reflect those worked PRIOR to the 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months holdover). All operators began their shift

schedule at the same time each day.

NOTE: A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months occurred between all work periods.

8

DAY 1 2 3 4 5 6 7

(today)

JPM OVERALL STANDARD: Determines that Reactor Operators #I, #3, #4,& #5 are not within

guidelines. Determines that Reactor Operator #2 is within guidelines.

\

SRO Adrnin A-la JPM

ii PAGE 3 OF 3

STEPS ELEMENTS STANDARD COMMENT

REQUIRED

FOR UNSAT

1 Compare hours worked Determines that RO#I

by ROW to NSD-200 would exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in

guidelines a 7 day period and would

require an overtime

authorization.

2 Compare hours worked Determines that RO#2

by RO#2 to NSD-200 would not exceed any

guidelines overtime restrictions and

could be held over for the

three hours.

3 Compare hours worked Determines that RO#3

by RO#3 to NSD-200 would exceed 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months

guidelines straight and 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a

24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period (today)

and would require

overtime authorization.

Compare hours worked Determines that RO#4

by RO#4 to NSD-200 would exceed 28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months in

guidelines a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period between

days 3 and 4 and 72

hours in a 7 day period

and would require an

overtime authorization.

Compare hours worked Determines that RO#5

by RO#5 to NSD-200 would exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in

guidelines a 7 day period and would

require an overtime

authorization.

INITIAL CONDITIONS

Due to plant startup activities, an Reactor Operator must be held over for the following shift for

three (3) hours.

Evaluate the following five Reactor Operators for availability to work 3 more hours without

an Overtime Extension and determine if the hours worked has exceeded NSD-200

requirements. State @ requirements that are violated, if applicable.

The following is the work history (excluding shift turnover time) of the available Reactor Operators

on shift (hours reflect those worked PRIOR to the 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months holdover). All operators began their shift

schedule at the same time each day.

NOTE: A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months occurred between all work periods.

VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR TO EACH USE

Nuclear Policy Manual - Volume 2 NSD 200

APPENDIX A.200. REQUEST FOR WORK HOURS EXTENSION

1. Permission is requested for the individuals listed below to exceed the guidelines ofTech Spec 5.2.2 for

hours that will be worked on the date shown. (Fill out ALL columns including: Full name, actual date

work hour extension will occur, the letter(s) of the limit(s) that will be exceeded, estimated hours that will

be worked beyond guidelines, Emp. ID, department or vendor name and assigned supervisor's name.)

NAME DATE/TIME LIMIT EST. HRS. Emp. ID DEPARTMENT/ ASSIGNED

(Print First, MI & Last Name) THE a, b, c, EXCEEDING (Same as VENDOR NAME SUPV

WORK d,e GUIDELINE Badge NAME

I EI

I BEGINS I

I I Number) II I

a. Working more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shift turnover time)

\--.., b. Working more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period (excluding shift turnover time)

C. Working more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (28 hours3.240741e-4 days 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months for MNS and ONS) in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period (excluding shift

turnover time)

d. Working more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period (excluding shift turnover time)

e. Less than 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months break between scheduled work periods (excluding callouts, hut including shift

turnover time).

Note: Call-outs are not considered scheduled work periods and do not require an Appendix A

form unless limit(s) a, b, c, d is exceeded due to the call-out. FFD and Management Procedures

- provisions apply to call-outs).

2. Specific reasons describing the need for exceeding the work hour guidelines. (Brief description of work to

be performed and why specific individuals are needed to complete task.

3. I have assessed the fitness for continued duty of the above named individual(s). The assessment included

an evaluation of the working conditions, and the individual(s) mental and physical ability to complete the

task safely. I find the individual(s) fitness satisfactory to safely complete the assignment. I will

I periodically re-assess their status as appropriate to determine their ability to continue. NOTE: The FFD

assessment must he done within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to the beginning of the task dateitime the work hour

extension begins.

Signed: Supv. ID: Date: Time:

SupervisoriTemp. SupervisoriDesignee of employee(s)/vendor(s)*

22 M A R 2001 5

VERIFY HARD COPY AGAINST WEB SITE IMMEDIATELY PRIOR T O EACH USE

COMMON

JPM

SRO Admin A-2 JPM

PAGE 1 OF4

!

b!

Reviewed By

Approved By

TASK: Evaluate Work Order and provide Clearance to work.

POSITION: SRO

Operator's Name

Validation Time: 20 minutes

Location: SimulatorlPlant Method: Perform

k.)The JPM Operator's performance was evaluated against the standards of this JPM and

is determined to be:

SATISFACTORYIUNSATISFACTORY (circle one)

Evaluator's Signature Date I I

-

References:

JPM verified current with references by

Date I I

Rev. 01103-26-03

SRO Admin A-2 JPM

PAGE 2 OF 4

\

L/

INITIAL CONDITIONS

Today is 06/16/03at 0700.

WO # 98313609-01 is on the Work Schedule for 06/16/03at 0700.

WO # 98313609-01is a PM on the 1A CA Pump coupling.

ORAM/Sentinel will be in the Yellow condition due to WO # 98313609-01.

As the WCC SRO you are to evaluate the Work Order and provide Clearance for

work.

JPM OVERALL STANDARD: Work Order is evaluate and Clearance for work is

given.

NOTES: If requested by candidate, provide attached Job Aid (Flowpath to Sign On

k., Work Orders).

Steps #2 through #6 of JPM can be performed in any order.

\ SRO Admin A-2 JPM

u PAGE 3 OF 4

START TIME

TEPS ELEMENTS STANDARD COMMENTS

REQUIRED

FOR UNSAT

~

1 'VCC SRO checks WO Verify Time on WO

3 on schedule. against Schedule.

Given Initial

Conditions

2 VCC SRO checks if Verify that a MOD is

VO is MOD related. not listed on WO if it is

verify that MOD review

sheet is signed

WO is not MOD

3 NCC SRO verifies If PRA field is coded

??A field is coded with a code other than

"No Code" ensure WO

is in scheduled time

slot

Given lnitial

Conditions

4 NCC SRO checks if Verifies component

NO is for a T.S. against T.S.

omponent Reference Manual

Section 3

T.S. 3.7.5Auxiliary

Feedwater System,

Condition B, Required

Action B.l

CUE:

TSAIL entry made by

night shift WCC SRO

MI-03-01384 for ?A

CA pump

4

-

DENOTES CRITICAL

SRO Admin A-2 JPM

i ,

PAGE 4 OF 4

~~~

STEPS ELEMENTS STANDARD s/u COMMENTS

REQUIRED

FOR UNSAT

5 WCC SRO checks if Verifies RED TAG and

WO requires OPS Red R&R fields on WO

Tags state that red tags are

required.

CUE:

R&R I-1119placedby

night shift WCC SRO

WCC SRO checks Checks that

configuration control configuration of

requirements are met. components will be

controlled by R&R or

other papenvork

(R&R is placed)

u ... ~

WCC SRO provides WO is signed in

Clearance for work Clearance field and

TSAIL number is

placed in TSAIL field

STOP TIME

i/__ * DENOTES CRITICAL

- Flowpath To Sign On WiOS

--

- - I

A A A A

-1 rba*

See SWMNVWM Isworkon

schedule?

4 Review WMS R121, R212, R214,

R362 for more info, as required

See SWMNVWM Signed MOD

Review sheet?

See S W W W M

coded?

See SWMNVWM

time slot?

INITIAL CONDITIONS

Today is 06116/03 at 0700.

WO # 98313609-01 is on the Work Schedule for 06/16/03 at 0700.

WO # 98313609-01 is a PM on the 1A CA Pump coupling.

ORAMlSentinel will be in the Yellow condition due to WO # 98313609-01

As the WCC SRO you are to evaluate the Work Order and provide Clearance for

work.

UNIT: 1 1

11

03/26/03 MCGUIRE NUCLEAR STATION 1

13:42:08 CREW COVER SHEET FOR WO#/TSK 1

ir38313609 0 1 CREW NUMBER:416 FOR :( 2003/&0/fb/ 0700 ) 11111

4ORK OROER T I T L E : PM-1CAPUOOOl-(COUPLING)-1A MOTOR DRIVEN CA PUMP-

WORK AGAINST : MC 1 CA PUOOOl PREDEFINED

98313609-01

EQUIPMENT DESC : 1A AUXILIARY FEEDWATER PUMP

__ _... - -.. - DO30

LOCATION

IOCATTON ---- :. AUXCC 50 0600

~~ . . 716

~

LOC NARR DESC : AUX 716 RM600 CC50, U 1 CA PUMP ROOM

EQUIPMENT L I S T NUM: 85054446 EQUIP TAG: lCAPUOOOl

TASK DESCRIPTION : PM-1CAPUOOOl-fCOUPLING~-lA CA PUMP

SAFETY-INSTRUCTION: USE SAFE WORK'PRACTICES, USE PROPER PPE

SPECIAL INSTRUCTN :

CLEARANCE : OPS DATE : PRA: CA-PO01

FEM:TECH SPEC RELATED: Y EXP. DATE/TIME:

SPECIAL EMPHASIS: CC CONTINUOUS COVERAGE

CE COMPLEX EVOLUTION

PR PROBABILISTIC RISK ASSESSMENT INTERACT10

TS TECH SPEC

9 DETAILED TSK DESC : PM-lCAPUOOOl-(COUPLING)-1A CA PUMP

A. DISASSEMBLE COUPLING, CLEAN OUT OLD GREASE

B . GREASE/REASSEMBLE COUPLING

C. ALIGN COUPLING

PROC/STO: * MP/O/A/7300/056 H o r i z o n t a l R o t a t i n g Equipment C o u p l i n g Alignment-

NSD104/FME REF PRE-JOB BRIEFING & FME EXEC STD PLN

POWERCHEMISTRYMANUAL PCMG MAY APPLY TO T H I S JOB, REFERENCE EWP 7.6-

DETERMINATIONS

QA CONDITION : 1 QC REQ. : Y RWP# : 20 RED TAG : OPS RED TAG

CONT CLOSURE : N RETEST : N RWP I N 0 : Y BTO# : N

CONTL RM I N D : N FUNC : N ALARA : N BT02# : N

CLEAN ZONE :4 ooc NPRDS :Y R 8 R : 1-1119

DUKE/ISI CLS : B / SIZE ACTIVE : CRIP : N

ii

- '1

- - SDOA CAT E --- FOR CONTROL COPY, REFER TO ELECTRONIC DATA ***

~~

UNIT: 1 ..1

A I

03/26/03 MCGUIRE NUCLEAR STATION 1

13:42:08 CREW COVER SHEET FOR WO#/TSK 1

c ~ J 8 3 1 3 6 0 90 1 CREW NUMBER:416 FOR :( 20010515 / 0700 ) 11111 /-

MODEL WO : 85054446 DUE DATE : 20010305 LATE DATE: 20020306 FREQ: 4Y

O R I G WR : W/O PRI : I PROJ

WO/TSK TP: PM /PM CRAFT : MP R121 Y/N : Y

JOB STAT : CLOSED TSK STAT : CLOSED DOC/PEND : *DOCCNTL

REFERENCE DRAWINGS :

LOC MC -1201-04.00 FLW MCFD-1592-01.01 6-4

DBD MCS-1154.00-00-0003 DBD MCS-1399.03-RPS-0001

DBD MCS-1465 .OO-00-0001 DBD MCS-1465.00-00-0014

DBD MCS-1465.00-00-0015 DBD MCS-1554-NV-00-0001

DBD MCS-1563.NS-00-0001 DBD MCS-1572.NM-00-0001

DBD MCS-1593.SA-00-0001 OBD MCS-1599.RF-00-0001

- C O R R E C T COMPONENT VERIFICATION

IDENTIFIED BY: UNIT: - DATE: TIME:

i /

VERIFIED BY: UNIT: - DATE: TIME:

- VERIFICATION OF SAFE WORKING CONDITIONS

VERIFIED BY: DATE: TIME:

- TASK COHPLETION

JOB SUPV: DATE:

ii

- - SDQA CAT E --- FOR CONTROL COPY, REFER TO ELECTRONIC DATA ***

UNIT: 1

03/26/03 MCGUIRE NUCLEAR STATION

13:42:08

L)-TSK: 98313609-01

,QUIPMENT LIST # : 85054446 ------ ADDITIONAL EQUIP. NO. ASSOCIATED WITH lMCAPUOOOl

STEP EQUIP NUM LOCATION

MC 1 CA MROOOl CA PUMP ROOM N SIDE 1A CAP

UNIT __ COMP VERIF ID: COMP VERIFIED BY:

i/

- - SOQA CAT E --- FOR CONTROL COPY, REFER TO ELECTRONIC DATA ***

SRO Admin A-3 JPM

Page 1 of 3

/7

' Reviewed By

ii

Approved By

TASK: Evaluate LWR Paperwork

POSITION: SRO

Operator's Name

Validation Time: 20 Minutes

Location: SimulatorlPlant Method: Perform

_-

ii The JPM Operator's performance was evaluated against the standards of this JPM and

is determined to be:

SATISFACTORYIUNSATISFACTORY(circle one)

Evaluator's Signature Date I I

-

References: OP/O/N6200/106 Liquid Waste Release - WMT A with WMT Pump A

JPM verified current with references by

Date I I

Rev. 01103-26-03

SRO Admin A-3 JPM

Page 2 of 3

u INITIAL CONDITIONS

The following conditions exist:

Unit 1 is at 100% power with 3 RC pumps running

Unit 2 is in No Mode with all RC pumps tagged

LWR Number 2001 182 for WMT A is scheduled to be performed

OP/O/A/B/6200/106 is complete up to step 3.15

The following are operable:

OEMF49

WMFlowLoop

IWP-35

IWP-37

RP brings the Liquid Waste Release Permit Report and OPIOIB/6200/106 End. 4.3

---%.%

to the Control Room and ask the Control Room SRO to perform step 3.15

JPM OVERALL STANDARD: Identifies errors in Liquid Waste Release Permit

Report and directs RP to correct errors.

NOTES: N/A.

,1 SRO Admin A-3 JPM

\/

Page 3 of 3

START TIME

-

jTEPS ELEMENTS STANDARD

REQUIRED

FOR UNSAT

1 CR SRO verifies Given in Initial

OEMF49 Conditions

WMFlowLoop

IWP-35

IWP-37

are operable.

2 CR SRO verifies LWR Given in Initial

Number and Release Conditions

ID on LWR Permit

Report

3 CR SRO verifies RC Recognize the Total

PUMP DATA on LWR RC pumps required

Permit Report (4) Should not be >

RC pumps running (3)

EVALUATOR NOTE:

If student stops here,

ask them to continue

their review of the

- .. LWR Permit Report.

4 CR SRO verifies Recognize the

RECOMMENDED Recommended

RELEASE DATA on release rate (120 gpm)

LWR Permit Report Should not be > the

Allowable release rate

(100 gpm)

CR SRO verifies Recognize the

SETPOINT DATA on Expected CPM

LWR Permit Report (4.56E+04) Should

not be > the Trip 2

set point

STOP TIME

i/

DENOTES CRITICAL

INITIAL CONDITIONS

The following conditions exist:

Unit 1 is at 100% power with 3 RC pumps running

Unit 2 is in No Mode with all RC pumps tagged

LWR Number 2001 182 for WMT A is scheduled to be performed

OP/O/A/B/6200/106 is complete up to step 3.1 5

The following are operable:

OEMF49

WM FIOWLOOP

IWP-35

IWP-37

RP brings the Liquid Waste Release Permit Report and OP/O/B/6200/106 End. 4.3

i/

to the Control Room and ask the Control Room SRO to perform step 3.15

RETDAS v3.5.0 <DPCMNS Rev.3.0> VSSI

LWR Number: 2001182

LIQUID WASTE RELEASE PERMIT REPORT

__________________________________

Release ID: Waste Monitor Tank "A"

c copy

/

=== RC puMp DATA .....................................

RC pumps running ....................................................... 3.00

RC pumps assigned to RELEASE ........................................... 2.00

Total RC pumps required (all concurrent releases) ......................

____-- 4.00

--

== RECOMMENDED RELEASE RATE --

--

Allowable release rate (gpm) ...................................... 1.00E+02

Recommended release rate (gpm) .................................... 1.20E+02

=_ SETpOIm DATA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

EMF49L in Service ................ Yes Source Checked By:

Monitor Background (cpm) ...... 2.23E+03

Cs-137 Equivalence (uCi/ML)... 6.813-06

Expected CPM .................. 4.563+04 EMF49L Trip 1 & 2

Trip 1 setpoint (cpm) ........ 9.5633+03

Trip 2 setpoint cpm) ........ 1.201E+04

Set by:

%

Performed by:

.- N e d by: !5&

=== Special Instructions For Release:

Initiate Release Prior to:

i/

SRO Authorization: Date/Time

Release-Initiation Release Completion

R P R C pump Permissive Set to Chem __ Rel. stop

Date Time

Chem -Rel. Start Chem -Vol. Released Gal

Date Time

Chem -# RC Pumps Running RC Pump Permissive As Found-

Chem

Completion of Release Acknowledged

OPS SRO Date/Time

RP Shift Review Date/Time

Date/Time: 09/01/2001 1O:lO Page - 2

Duke Power Company Procedure No.

McGuire Nuclear Station OP/ o/B/6200/106

Revision No.

010

-

Liquid Waste Release WMT A with WMT

Pump A

Electronic Reference No.

MC00471L

Continuous Use

PERFORMANCE

This Procedure was printed on 03/26/03 at 13:54:46 from the electronic library as:

(ISSUED) - PDF Format

Compare with Control Copy every 14 calendar days while work is being performed.

Compared with Control Copy Date

- ..

Compared with Control Copy Date

ii Date(s) Performed Work Ordermask Number (WO#)

I

COMPLETION

Yes NA

0 0 Checklists and/or blanks properly initialed, signed, dated, or tilled in NA, as appropriate?

0 0 Listed enclosures attached?

0 0 _Data sheets attached, completed, dated, and signed?

0 0 Charts, graphs, etc. attached and properly dated, identified, and marked?

0 0 Procedure requirements met?

Verified By Date

Procedure Completion Approved Date

Remarks (attach additional pages, fnecessary)

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 1 of 21

\

ii

Continuous Use

LWR# DATA TRANSFER #

1. Limits and Precautions

1.1 Discharge recorder OWMCR5130 (Waste Mon Tank Pumps Disch Flow) is normal

instrument for verifying flow. WMT releases must be made with proper verification of

release flow rate. Release may continue indefinitely provided SLC Section 16.11

(Radiological Effluent Controls), Action 4, Table 16.11-2 provisions are followed.

1.2 WMT pH range is greater than 2.0 and less than 12.5. A pH outside of 2.0 - 12.5 range

constitutes Hazardous Waste and requires Chemistry Management notification.

1.3 OEMF49 (Liquid Waste Disch Radiation Monitor) must be operable with operable

AlamdTrip Setpoints to ensure SLC 16.11-1 limits are NOT exceeded. Release may

continue indefinitely provided SLC Section 16.11 (Radiological Effluent Controls),

Action I, Table 16.11-2 provisions are met.

. -.. 1.4 WMT A may be released using WMT Pump B per OP/O/B/6200/035 (Discharging A

Waste Monitor Tank To The Environment). WMT Pump B must be used to obtain

release sample if WMT A release to be performed using WMT Pump B and valve

u alignment must remain unaltered to prohibit unanalyzed waste being added to discharge

stream because of additional piping use.

1.5 OWMPG5110 (A Waste Monitor Tank Pump Disch Press) must be operable to release

using WMT Pump A. Release may be performed with WMT Pump B per

OP/O/B/6200/035 (Discharging a Waste Monitor Tank to the Environment).

1.6 OWMLT5090 (A Waste Monitor Tank Level) must be operable to perform release.

1.7 WHEN 1WP-35 (Turbine Building Sump Pumps to RC Isol) 1WP-37

(Turbine Building Sump Pumps to RC Isol) inoperable, release to be performed using

Enclosure 4.10 (WMT A Release Using WMT Pump A With 1WM-46).

1.8 WHEN OWMCR5130 (Waste Mon Tank Pumps Disch Flow) OWMFT5130

(A Waste Monitor Tank Pump Disch Flow) inoperable, release to be performed per

Enclosure 4.5 (WMT A Release With OWMCR5130 Or OWMFT5130 Inoperable).

1.9 WHEN OEMF49 inoperable, release to be performed per Enclosure 4.4

(WMT A Release With OEMF49 Inoperable).

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 2 of 21

y;

1.10 Hydrazine (NzK) is a strong reducing agent and has been identified as a known

carcinogen. h4NS NPDES permit restricts discharge canal concentration to less

than 0.06 pprn hydrazine. WMTs do NOT need to be monitored for hydrazine on a

routine basis, only when process knowledge indicates an input of hydrazine to WMT.

Enclosure 4.1 (Allowable Chemical Concentration at RC Discharge) must be adhered to

in determining allowable concentration of hydrazine in a WMT.

1.11 Nitrite (NO;) is a reducing agent that has a mandated EPA release limit. The release

limit or Reportable Quantity (RQ) is 100 pounds for any 24-hour period. Nitrite

concentration shall be monitored anytime process knowledge indicates an input of nitrite

into Wh4 System. Nitrite analysis NOT required when known concentration of nitrite is

900 ppm or less. Enclosure 4.2 (Nitrite Poundage Calculation for a WMT) must be

adhered to in determining nitrite poundage in WMT.

1.12 WMT Boron concentration only monitored when process knowledge indicates discharge

canal concentration of greater than 0.75 ppm (administrative limit) will be exceeded.

Enclosure 4.1 (Allowable Chemical Concentration at RC Discharge) must be adhered to

in determining allowable release concentration based on number of RC Pumps in

operation.

,*. .

1.13 Release of ethylene glycol to the environment limited to 55 gallons of 50% glycol or

25 gallons of 100% glycol per WMT. The discharge canal concentration of less than

'ii 1.0 ppm (administrative limit) with two RC Pumps in operation will NOT be exceeded

at these quantities.

1.14 releasing water, other than Laundry water, that has NOT been processed through

appropriate demineralizers, (i.e., process train inoperable, all components or plant

conditions are such that water CANNOT be processed) Chemistry Supervision must be

notified. A decision will be made by Supervision as to whether or NOT RP Shift should

be notified to perform PT/O/B/4600/020 (Thirty One (31) Day Offsite Dose Projection).

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 3 of 21

'

i

u:" 2. Initial Conditions

All of the following are operable and available for use:

id OWMPG5110 (A Waste Monitor Tank Pump Disch Press)

d OWMLT5090 (A Waste Monitor Tank Level)

d OEMF49 (Liquid Waste Disch Radiation Monitor)

d WM Flow Loop (Le., OWMCR5130 (Waste Mon Tank Pumps Disch Flow) or OWMFT5130

(A Waste Monitor Tank Pump Disch Flow)

d 1WP-35 (Turbine Building Sump Pumps to RC Isol)

d 1WP-37 (Turbine Building Sump Pumps to RC Isol)

id 1WMPU0038(A Waste Monitor Tank Pump)

<-

.. ,

3. Procedure

d3.1 Evaluate all outstanding R&Rs and Special Orders that may impact performance of this

u procedure.

& 3.2 Close 1WM-103 (A Waste Monitor Tank Inlet Isol).

& 3.3 Start WMT Pump A.

& 3.4 E WMT A Flash Mixer operable, start Flash Mixer and recirc tank a minimum of

30

- minutes.

3.5 WMT A Flash Mixer inoperable, recirc tank a minimum of 60 minutes.

& 3.6 Throttle 1WM-106 (A Waste Monitor Tank Pump Recirc Throttle) as necessary to

maintain pump discharge pressure between 87 - 110 psig as indicated on OWMPG5110

(A Waste Monitor Tank Pump Disch Press).

A 3.7 WHEN recirc and mixing requirements met, sample WMT A per CP/O/B/8600/001

(Radwaste Sampling).

3.8 E in service, stop WMT A Flash Mixer.

Ce, 3.9 stop WMT Pump A.

70% 3.10 Record WMT A level as indicated on OWMPS5091 (Waste Monitor Tank A Level).

' ! LEVEL

Enclosure 4.3 OP/OB/6200/ 106

WMT A Release Using WMT Pump A Page 4 of 21

b NOTE: Acceptable pH range is 2.0 - 12.5.

&

' 3.1 1 Record Wh4T A sample pH result.

PH

d3.12 Record Target Activity Level in Step 3.14.1.

cY'3.13 Record Data Transfer number on the following and take to Count Room:

0 WMTASample

Enclosure Working Copy

3.14 RP to perform the following:

C i L 3.14.1 Ensure WMT BetdGamma Results are below 5 - pCi/ml (Target

RP Activity Level). [PIP M-98-01938)

2 . 5 'Swi/rnl = ;2.5f-.<@Urn1 - wi/rnl

BetdGamma Grand Total Activity Fission Gas Total Activilj'

3.14.2 BetdGamma results are greater than Target Activity recorded in

Step 3.14.1, notify Radwaste Chemistry prior to processing paperwork.

u

Radwaste Contact

d3.14.3 Attach LWR Discharge Document and two copies of Liquid Waste Release

(LWR) Permit Report, Page 1 (Nuclide Data) to this Enclosure, herein after

referred to as LWR Document.

3.14.4 Set trip setpoints for O E m 4 9 per H'/O/B/1003/008 (Determination of

RP Radiation Monitor Setpoint [ E m s ] ) .

d3.14.5 Take LWR Document to CR SRO.

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 5 of 21

\

' 3.15 CR SRO to perform the following:

1 NOTE: CR SRO to place signature in space provided after Step 3.15.5. I

-3.15.1 -

IF any of the following are inoperable, notify Radwaste Chemistry and return

LWR Document.

OEMF49 (Liquid Waste Disch Radiation Monitor)

WM Flow Loop (Le., OWMCR5130 (Waste Mon Tank Pumps Disch Flow) or

OWMFT5130 (A Waste Monitor Tank Pump Disch Flow)

1WP-35 (Turbine Building Sump Pumps to RC Isol)

0 1WP-37 (Turbine Building Sump Pumps to RC Isol)

-3.15.2 Ensure applicable items on LWR Document complete and sign if approved for

release.

,---\

-3.15.3 Ensure OEMF49 source check performed.

-3.15.4 -IF desired place trace recorder EMFCR0020 in service for OEMF49.

b

3.15.5 Record LWR # on Page 1 of this Enclosure.

I -

CR SRO Contact Date Time

0 3.16 RP to return LWR Document to Radwaste Chemistry.

-3.17 -

IF LWR Document returned due to inoperability of OEMF49, close this Enclosure and

perform release using Enclosure 4.4 (WMT A Release With OEMF49 Inoperable).

__ 3.18 -

IF LWR Document returned due to inoperability of 1WP-35 (Turbine Building Sump

Pumps to RC Isol) 1WP-37 (Turbine Building Sump Pumps to RC Isol), close this

Enclosure and perform release using Enclosure 4.10 (WMT A Release Using WMT

Pump A With 1WM-46).

-3.19 -

IF LWR Document returned due to inoperability of WM Flow Loop, close this

Enclosure and perform release using Enclosure 4.5 (WMT A Release With

OWMCR5130 Or OWMFT5130 Inoperable).

0 3.20 Check "Initial Conditions" continue to be met since initiation of Enclosure.

u 3.21 Check required signatures appear on LWR Document.

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 6 of 21

\

i/ 3.22 Ensure required analyses are complete and within administrative limits as listed below:

PH 2.0 - 12.5

Nz& e 0.06 ppm

NO? 100 pounds

Ethylene Glycol 55 gallons of 50% or 25 gallons of 100%

__ 3.23 Notify CR SRO Liquid Waste Release is ready to initiate.

CR SRO Contact

~

NOTE: Step 3.24 to be performed with CRO via phone. CRO name to be documented in space

provided after Step 3.24.7.

3.24 Read the following steps to CRO and obtain required verifications: {PIP M-95-00985)

17 3.24.1 Check in "NORMAL" position "RC PUMPS BYPASS PERMISSIVE'

switch.

ii

-3.24.2 E "RC PUMPS BYPASS PERMISSIVE inoperable AND switch _NOT in

"BYPASS" position, obtain CRO permission and place switch in "BYPASS"

position. {PIP M-98-04262) {PIPM-95-00985)

0 3.24.3 Compare actual number of RC Pumps in-service to required number of RC

Pumps in-service per LWR Document.

__ 3.24.4 E required number of RC Pumps NOT in-service, request CRO place

required number of RC Pumps in-service.

3.24.5 Request CRO provide notification if required number of RC Pumps in-service

-

NOT maintained during release.

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 7 of 21

NOTE: IRC-21 (RC Crossover Disch Isol) and 1RC-22 (Unit 1 RC to Unit 2 RC Crossover

Disch Isol) are closed to prevent pumping tank contents to WC System via Turbine

Building (TB) Sump.

-3.24.6 E all Unit 1 RC Pumps off, request CRO check closed 1RC-21

(RC Crossover Disch Isol).

___ 3.24.7 E all Unit 2 RC Pumps off, request CRO check closed 1RC-22

(Unit 1 RC to Unit 2 RC Crossover Disch Isol).

- I-

CRO Contact Date Time

-3.24.8 Obtain CRO permission and perform the following: {PIP M-95-00985)

- -3.24.8.1 Ensure open 1WP-35 (Turbine Building Sump Pumps to RC Isol)

CHM CROW and request CRO to Separately Verify position which will be

documented via phone.

- -3.24.8.2 Ensure open 1WP-37 (Turbine Building Sump Pumps to RC Isol)

CHM CROSV and request CRO to Separately Verify position which will be

documented via phone.

__ 3.25 Open 1WM-45 (OEMF49 Outlet Isol to RC Cond Disch).

__ 3.26 Open IWM-245 (OEMF49 Bypass).

3.27 Ensure open:

___ 1WM-294 (OEMF49 Outlet Isol)

-9 1WM-295 (OEMF49 Inlet Isol)

3.28 Ensure closed:

- 1WM-117 (A Waste Monitor Tank Pump Recirc Through WM System)

- 1WM-240 (A Waste Monitor Tank Outlet to B Waste Monitor Tank Pump Isol)

__.- 3.29 Unlock and open 1WM-116 (A Waste Monitor Tank Pump Disch to OEMF49 Isol).

CHM DV {PIPM-99-05469)

__ 3.30 Ensure OWMCR5130 (Waste Mon Tank Pumps Discb Flow) "ON".

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 8 of 21

\

u -3.31 E OWMPS5091 (Waste Monitor Tank A Level) has NOT changed by more than 1%

since initially recorded in Step 3.10, go to Step 3.34.

-3.32 OWMPS5091 (Waste Monitor Tank A Level) indicates a greater than 1% tank volume

increase, perform the following:

-3.32.1 Notify Radwaste Chemistry Staff of increase in tank volume.

STAFF

0 3.32.2 Investigate change in tank volume.

0 3.32.3 Determine source of input and secure.

0 3.32.4 Attach explanation of increase in tank volume to this Enclosure, verified by

Radwaste Chemistry Staff.

0 3.32.5 Close this Enclosure and initiate new Enclosure to release WMT A.

-3.33 E OWMPS5091 (Waste Monitor Tank A Level) indicates a decrease of more than 1%

tank volume, perform the following:

__ 3.33.1 Notify Radwaste Chemistry Staff of decrease in tank volume.

STAFF

0 3.33.2 Investigate change in tank volume.

ii

0 3.33.3 Attach explanation of decrease in tank volume to this Enclosure, verified by

RadwasteChernistry Staff.

-3.34 Start WMT Pump A.

-3.35 -

IF operable, start WMT A Flash Mixer.

__ 3.36 Check OWMFS5440 (OEMF49 Outlet Flow) indicates zero.

-3.31 Request CRO assistance to initiate release (via phone).

CRO Contact

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 9 of 21

\

1

w, NOTE: Discharge flow rate normally obtained at 100 - 110 psig as indicated on OWMPG5110

(A Waste Monitor Tank Pump Disch Press).

3.38 Initiate discharge flow at or below flow rate specified on LWR Document:

-3.38.1 Slightly throttle open 1WM-114 (A Waste Monitor Tank Pump Disch

Throttle).

-3.38.2 Close 1 W - 1 0 6 (A Waste Monitor Tank Pump Recirc Throttle).

-3.38.3 Throttle 1WM-114 (A Waste Monitor Tank Pump Disch Throttle) until

required discharge flow obtained as indicated on OWMPG5110 (A Waste

Monitor Tank Pump Disch Press).

__ 3.39 Throttle closed 1WM-245 (OEMF49 Bypass) until 3 - 6 gpm flow through OEMF49

obtained as indicated on OWMFS5440 (OEMF49 Outlet Flow).

__ 3.40 -

IF flow through OEMF49 acceptable OEMF49 Low-Flow Alarm enables and

clears, request CRO to notify Radwaste Chemistry of any OEMF49 alarms received

during LWR.

i/ CRO Contact

__ 3.41 -

IF in-service, stop WMT A Flash Mixer.

__ 3.42 -

IF required flow CANNOT be obtained through OEMF49, perform the following:

- 3.42.1 Close 1WM-114 (A Waste Monitor Tank Pump Disch Throttle).

-3.42.2 Throttle = 1% turns open 1WM-106 (A Waste Monitor Tank Pump Recirc

Throttle) to maintain pump discharge pressure between 87 - 110 psig as

indicated on OWMPG5110 (A Waste Monitor Tank Pump Disch Press).

-3.42.3 Open 1WM-245 (OEMF49 Bypass).

Enclosure 4.3 OP/O/B/6200/ 106

WMT A Release Using WMT Pump A Page 10 of 21

>'

LJ- 3.42.4 Notify CRO, Radwaste Chemstry Staff and RP that LWR terminated due to

inability to meet OEMF49 flow requirement.

CRO Contact

Radwaste Chemistry Staff Contact

RP Contact

3.42.5 Investigate inability to meet flow requirement through OEMF49.

3.42.6 LWR to be re-initiated, perform Enclosure 4.6 (Re-Initiation Of WMT A

Release Using WMT Pump A).

__ 3.42.7 OEMF49 determined inoperable, perform the following:

-3.42.7.1 Stop W m Pump A

__ 3.42.7.2 Record WMT A level.

LEVEL

-3.42.7.3 Record LWR stop time here and on LWR Document.

TIME

- -3.42.7.4 Lock closed IWM-116 (A Waste Monitor Tank Pump Disch to

CHM DV OEMF49 Isol). {PIPM-99-05469)

-3.42.7.5 Notify CR SRO and declare OEMF49 inoperable.

1

-

CR SRO Contact Date Time

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 11 of 21

__ 3.42.7.6 Notify CRO and RP of the following:

LWR terminated due to OEMF49 faiIure.

Total volume released prior to OEMF49 failure.

OEMF49 declared inoperable.

Volume Released: gallons

CRO Contact

RP Contact

3.42.7.7 Prepare Special Order per Chemistry Manual Section 2.1 1

(Chemistry Special Orders and Equipment Operability Log) to

document OEMF49 inoperability.

__ 3.42.7.8 Close 1WM-45 (OEMF49 Outlet Is01 to RC Cond Disch).

__ 3.42.7.9 Close 1WM-245 (OEMF49 Bypass).

'v'

3.42.7.10 Stamp Chart Recorder and record required information.

3.42.7.1 1 Close this Enclosure and perform release using Enclosure 4.4

(WMT A Release With OEMF49 Inoperable).

NOTE: WMT A denoted by Pen #1 on OWMCR5130 (Waste Mon Tank Pumps Disch Flow).

__ 3.43 Ensure release flow rate less than or equal to that allowed by LWR Document.

3.44 Stamp Chart Recorder and record required information.

3.45 Record LWR start time here and on LWR Document.

TIME

__ 3.46 Notify RP of LWR start time.

RP Contact

3.47 Update LWR Document.

Enclosure 4.3 0P/oIB/6200/106

WMT A Release Using WMT Pump A Page 12 of 21

\

u 3.48 Monitor LWR and perform the following as required

-3.48.1 E High Rad Trip occurs during LWR, go to Step 3.50.

NOTE: WM Flow Loop is comprised of the following:

OWMFE5130 (A Waste Monitor Tank Pump Disch Flow)

OwMFT5130 (A Waste Monitor Tank Pump Disch Flow)

OWMP5130 (A Waste Monitor Tank Pump Disch Flow)

OWMPE5130 (A Waste Monitor Tank Pump Disch Flow)

OWMPS5130 (A Waste Monitor Tank Pump Disch Flow)

WHEN OWMCR5130 (Waste Mon Tank Pumps Disch Flow) OR OWMlT5130

(A Waste Monitor Tank Pump Disch Flow) are inoperable OR removed from service

for any reason, inoperability to be logged with CR SRO.

-3.48.2 OEMF49,0WMCR5130 (Waste Mon Tank Pumps Disch Flow) OR

OWMlT5130 (A Waste Monitor Tank Pump Disch Flow) fail during LWR,

go to Step 3.51.

-3.48.3 E Site Assembly occurs during LWR, go to Step 3.52.

u -3.49 Stop WMT Pump A at = 10% level in WMT A and go to Step 3.53.

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 13 of 21

NOTE: 1. E for any reason 1WP-35 (Turbine Building Sump Pumps to RC Isol) 1WP-37

(Turbine Building Sump Pumps to RC Isol) trip closed during LWR, it shall be

treated as a High Rad Trip.

2. 1WP-35 (Turbine Building Sump Pumps to RC Isol) will trip closed if preset

radiation level is exceeded on the following:

OEMF49 (Liquid Waste Disch Radiation Monitor)

1EMF44 (Unit 1 Cont VUCDT Disch EMF)

2EMF44 (Unit 2 Cont VUCDT Disch EMF)

3. 1WP-35 (Turbine Building Sump Pumps to RC Isol) or 1WP-37 (Turbine Building

Sump Pumps to RC Isol) will trip closed if no RC Pump breakers are closed

(i.e., at least one RC Pump must be running).

3.50 High Rad Trip:

-3.50.1 Close 1WM-114 (A Waste Monitor Tank Pump Disch Throttle).

-3.50.2 Throttle = 1% turns open 1WM-106 (A Waste Monitor Tank Pump Recirc

Throttle) to maintain pump discharge pressure between 87 - 110 psig as

indicated on OWMPG5 110 (A Waste Monitor Tank Pump Disch Press).

-3.50.3 Open 1WM-245 (OEMF49 Bypass).

0 3.50.4 Record WMT A level and time of High Rad Trip in appropriate space below:

High Rad Trip #1 High Rad Trip #2 High Rad Trip #3

Level:

Time:

Re-Initiation Time:

CRO Contact

RP Contact

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 14 of 21

\

u 0 3.50.6 Document High Rad Trip in Autolog.

-3.50.7 -

IF OEMF49 Control Room Alarm clears shortly after High Rad Trip AM)

prior to flushing, flush will NOT be necessary, go to Step 3.50.9.

0 3.50.8 Perform Enclosure 4.7 (OEMF49 Flush to Floor Drain Tank Sump),

0 3.50.9 Stamp Chart Recorder and record required information.

NOTE: A separate Working Copy of Enclosure 4.6 (Re-Initiation of WMT A Release Using

WMT Pump A) shall be used for each re-initiation attempt and attached to this Enclosure.

3.50.10 After High Rad Trip(s), perform the following as appropriate:

__ E High Rad Trip #I, perform Enclosure 4.6 (Re-Initiation Of WMT A

Release Using WMT Pump A).

__ High Rad Trip #2, perform Enclosure 4.6 (Re-Initiation Of WMT A

Release Using WMT Pump A).

__ E High Rad Trip #3, stop WMT Pump A and go to Step 3.53.

3.51 Failure of OEMF49,OWMCR5130 (Waste Mon Tank Pumps Disch Flow) or

OWMFT5130 (A Waste Monitor Tank Pump Disch Flow):

3.51.1 Close IWM-114 (A Waste Monitor Tank Pump Disch Throttle).

-3.51.2 Throttle = 1% turns open 1WM-106 (A Waste Monitor Tank Pump Recirc

Throttle) to maintain pump discharge pressure between 87 - 110 psig as

-~ indicated on OWMPG5110 (A Waste Monitor Tank Pump Disch Press).

-3.51.3 Stop WMT Pump A.

__ 3.51.4 Record WMT A level.

LEVEL

3.51.5 Record LWR stop time here and on LWR Document.

TME

- -3.51.6 Lock closed 1WM-116 (A Waste Monitor Tank Pump Disch to OEMF49 Isol).

CHM DV {PIPM-99-05469)

3.51.7 Close 1WM-45 (OEMF49 Outlet Isol to RC Cond Disch).

3.51.8 Close 1WM-245 (OEMF49 Bypass).

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 15 of 21

\

</ 3.51.9 Notify CR SRO and declare inoperable OEMF49 or WM Flow Loop

(i.e., OWMCR5130 (Waste Mon Tank Pumps Disch Flow) or OWMFT5130

(A Waste Monitor Tank Pump Disch Flow).

CR SRO Contact Date Time

3.51.10 Notify CRO and RP of the following:

LWR terminated due to failure of OEMF49 or WM Flow Loop.

Total volume released prior to failure.

OEMF49 or WM Flow Loop declared inoperable.

Volume Released gallons

CRO Contact

RP Contact

0 3.51.11 Prepare Special Order per Chemistry Manual Section 2.11 (Chemistry Special

Orders and Equipment Operability Log) to document OEMF49 or WM Flow

Loop inoperability.

-3.51.12 OWMCR5130 (Waste Mon Tank Pumps Disch Flow) operable, stamp

Chart Recorder and record required information.

0 3.51.13 Close this Enclosure and perform release using Enclosure 4.4 (WMT A

Release With OEMF49 Inoperable).

3.52 Site Assembly:

3.52.1 Close 1WM-114 (A Waste Monitor Tank Pump Disch Throttle).

-3.52.2 Throttle = 1% turns open 1WM-106 (A Waste Monitor Tank Pump Recirc

Throttle) to maintain pump discharge pressure between 87 - 110 psig as

indicated on OWMPG5110 (A Waste Monitor Tank Pump Disch Press).

3.52.3 Stop WMT Pump A.

3.52.4 Record WMT A level.

LEVEL

Enclosure 4.3 OP/O/B/6200/106

WMT A Release Using WMT Pump A Page 16 of 21

\

i / -3.52.5 OWMCR5130 (Waste Mon Tank Pumps Disch Flow) operable, stamp

Chart Recorder and record required information.

-3.52.6 OWMCRS130 (Waste Mon Tank Pumps Disch Flow) OWMlT5130

(A Waste Monitor Tank Pump Disch Flow) inoperable, document appropriate

information on Table 4.3-1.

__- 3.52.7 Lock closed 1WM-116 (A Waste Monitor Tank Pump Disch to OEMF49 Isol).

CHM DV [PIP M-99-05469}

-3.52.8 WHEN time permits, close:

- 1WM-45 (OEMF49 Outlet Is01 to RC Cond Disch)

- 1WM-245 (OEMF49 Bypass)

- -3.52.9 Notify CR SRO, CRO and RP that LWR terminated due to Site Assembly and

TME report volume released (total gallons) and time. {PIP M-95-00985)

Volume Released: gallons

CR SRO Contact

-\ ./

CRO Contact

RP Contact

NOTE: Step 3.56.1 may be performed in conjunction with Step 3.53.

__- 3.53 Notify CR SRO, CRO and RP that LWR complete and report volume released (total

TIME gallons) and time. [PIP M-95-00985)

Volume Released: gallons

CR SRO Contact

CRO Contact

RP Contact

Enclosure 4.3 OP/O/B/6200/ 106

WMT A Release Using WMT Pump A Page 17 of 21

\

i -3.54 -

/ IF OWMCR5130 (Waste Mon Tank Pumps Disch Flow) operable, stamp Chart Recorder

and record required information.

__ 3.55 -

IF flush performed after High Rad Trip #3 per Enclosure 4.7 (OEMF49 Flush to Floor

Drain Tank Sump), go to Step 3.57.

3.56 Flush OEMF49 and discharge piping as follows:

-3.56.1 Notify CR SRO and declare OEMF49 inoperable. {PIP M-96-00764)

CR SRO Date Time

~ 3.56.2 Notify RP OEMF49 declared inoperable.

RP Contact

3.56.3 Close:

- 1WM-106 (A Waste Monitor Tank Pump Recirc Throttle)

- 1WM-239 (A Waste Monitor Tank Pump Suction Isol)

3.56.4 Open:

- 1WM-107 (A Waste Monitor Tank Pump Dm Isol)

__ 1WM-111 (A Waste Monitor Tank Pump Tell-Tale)

3.56.5 Open:

- 1YM-140 (Demin Water Supply Is01 to Col KK-56 Elev 716)

__ 1YM-433 (A Waste Monitor Tank Pump Demin Water Flush Supply Isol)

NOTE: OEMF49 flow indicated on OWMFS5440 (OEMF49 Outlet Flow).

3.56.6 Close 1WM-245 (OEMF49 Bypass) to obtain maximum allowable flow

through OEMF49.

0 3.56.7 Flush OEMF49 until counts reduced to & 500 cpm of background counts

recorded on LWR Document.

Enclosure 4.3 OP/O/B/6200/106

.>' WMT A Release Using WMT Pump A Page 18 of 21

'* ..( -3.56.8 E additional flush required, open:

- 1YM-432 (OEMF49 Demin Water Flush Supply Isol)

__ IWM-291 (OEMF49 Inlet Sample Isol)

-3.56.9 additional flush used and is no longer required, close:

__ IYM-432 (OEMF49 Demin Water Flush Supply Isol)

- IWM-291 (OEMF49 Inlet Sample Isol)

-3.56.10 WHEN flush complete, close:

- 1YM-433 (A Waste Monitor Tank Pump Demin Water Flush Supply Isol)

- 1WM-111 (A Waste Monitor Tank Pump Tell-Tale)

___ 1WM-107 (A Waste Monitor Tank Pump Dm Isol)

,..-. -3.56.11 Open 1WM-239 (A Waste Monitor Tank Pump Suction Isol).

, -3.56.12 E OEMF49 counts CANNOT be reduced to * 500 cpm of background

43, - recorded on LWR Document, flush per one of the following enclosures:

0 Enclosure 4.7 (OEMF49 Flush To Floor Drain Tank Sump)

-OR

0 Enclosure 4.8 (WMT Pump A Flush To Floor Drain Tank Sump)

-

-OR

0 Enclosure 4.9 (OEMF49 Direct Flush)

NOTE: RP will initiate Work Request to decon OEMF49 as required. At RP discretion, OEMF49

may be declared inoperable if Trip 2 Setpoint CANNOT be set.

-3.56.13 E OEMF49 counts CANNOT be reduced to k 500 cpm of background

recorded on LWR Document, notify RP.

RP Contact

Enclosure 4.3 OP/o/B/6200/106

WMT A Release Using WMT Pump A Page 19 of 21

--.

\

\/ -3.56.14 OEMF49 remains inoperable after flush, prepare Special Order per

Chemistry Manual Section 2.1 1 (Chemistry Speclal Orders and Equipment

Operability Log) to document OEMF49 inoperability.

-3.56.15 E OEMF49 flush obtained desired results, notify CR SRO and declare

OEMF49 operable.

- /-

CR SRO Contact Date Time

__ 3.56.16 E OEMF49 declared operable, notify RP.

RP Contact

3.57 Close:

- 1WM-45 (OEMF49 Outlet Isol to RC Cond Disch)

- 1WM-245 (OEMF49 Bypass)

.*...

. - 3.58 Open 1WM-103 (A Waste Monitor Tank Inlet Isol).

/>./, -3.59 Close 1WM-114 (A Waste Monitor Tank Pump Disch Throttle).

-3.60 Throttle = 1% turns open 1WM-106 (A Waste Monitor Tank Pump Recirc Throttle).

3.61 Request the following information from CRO: (PIP M-99-04364}

0 Unit 1 or Unit 2 TB Sump being released to RC (YesJNo)

0 Unit 1 or Unit 2 VUCDT in Continuous Release (YesJNo)

CRO Contact

3.62 E Unit 1 Unit 2 VUCDT in Continuous Release, obtain CRO permission and

perform the following: (PIP M-95.00985)

__- 3.62.1 Ensure open 1WP-35 (Turbine Building Sump Pumps to RC Isol) and request

CHM CROW CRO to Separately Verify position which will be documented via phone.

__- 3.62.2 Ensure open 1WP-37 (Turbine Building Sump Pumps to RC Isol) and request

CHM CROW CRO to Separately Verify position which will be documented via phone.

Enclosure 4.3 OP/O/B/6200/ 106

WMT A Release Using WMT Pump A Page 20 of 2 1

-\

'hb.,l __ 3.63 Unit 1 or Unit 2 TB Sump being released to RC AND Unit 1 or Unit 2 VUCDT NOT

in Continuous Release, obtain CRO permission and perfom the following:

{PIP M-95-009851

- -3.63.1 Close 1WP-35 (Turbine Building Sump Pumps to RC Isol) per the following,

CHM CROSV and request CRO to Separately Verify position which will be documented via

phone.

__ Place "CONTROL SWITCH in "CLOSED" position and hold until valve

indicates closed.

- Release "CONTROL SWITCH allowing return to "AUTO" position.

- -3.63.2 Ensure open 1WP-37 (Turbine Building Sump Pumps to RC Isol) and request

CHM CROW CRO to Separately Verify position which will be documented via phone.

-3.64 Unit 1 or Unit 2 TB Sump being released to RC Unit 1 or Unit 2 VUCDT

-

NOT in Continuous Release, obtain CRO permission and perform the following:

{PIP M-95-009851

_._ - -3.64.1 Close 1WP-35 (Turbine Building Sump Pumps to RC Isol) per the following

CHM CROSV and request CRO to Separately Verify position which will be documented via

phone.

- Place "CONTROL SWITCH' in "CLOSED" position and hold until valve

indicates closed.

- Release "CONTROL SWITCH' allowing return to "AUTO" position.

- -3.64.2 Close 1WP-37 (Turbine Building Sump Pumps to RC Isol) per the following

CHM CROSV and request CRO to Separately Verify position which will be documented via

phone.

__ Place "CONTROL SWITCH" in "CLOSED" position and hold until valve

indicates closed.

__ Release "CONTROL SWITCH allowing return to "AUTO" position.

__ 3.65 "RC PUMPS BYPASS PERMISSIVE" switch placed in "BYPASS" per Step 3.24.2,

obtain CRO permission and return switch to "NORMAL" position. (PIP M-98-042621

{PIP M-95-00985)

-~ /

CRO Contact Date Time

u

Enclosure 4.3 OP/O/B/6200/ 106

WMT A Release Using WMT Pump A Page 21 of 21

.

i

- ,/ 0 3.66 Record "As Found" "RC PUMPS REQUIRED FOR DILUTION" switch position on

LWR Document.

- -3.67 Lock closed 1WM-116 (A Waste Monitor Tank Pump Disch to OEMF49 Isol).

CHM DV [PIP M-99-05469)

0 3.68 Complete LWR Document.

0 3.69 Take complete LWR Document to RP.

0 3.70 RP takes completed LWR Document to CR SRO.

3.71 CR SRO signs LWR Document.

0 3.72 RP keeps original LWR Discharge Document and forwards completed LWR Document

to Radwaste Chemistry.

0 3.73 Verify receipt of completed LWR Document including LWR Permit Report.

End of Enclosure

SRO Admin A 4 JPM

PAGE 1 OF 7

Reviewed By ,

4Approved By

TASK: Determine Protective Action Recommendations and

perform the initial notifications.

POSITION: SRO

Operator's Name

Location: Simulator Method: Perform

The JPM Operator's performance was evaluated against the standards of this JPM and is

determined to be:

,+--.,

SATlSFACTORY/UNSATlSFACTORY (circle one)

L'

Evaluator's Signature Date / I

KA: 194 007 A1.16

References: RP/O/A/5700/000 Classification of an Emergency

RP/O/A/5700/004 General Emergency

Attachments:

Rev. 02103-31-03

SRO Admin A 4 JPM

PAGE 2 OF 7

?

u INITIAL CONDITIONS

Assume: Today is Monday. It is now 0600 on MARCH 31

At 0545, the Reactor on Unit # I was tripped and Safety Injection initiated due decreasing

inventory and pressure.

A SGTR has occurred with an unisolable secondary line break on 1C S/G inside containment.

All CA pumps have just tripped off and due to inadequate SIG levels, a valid Heat Sink Red

Path is in effect.

The event has been announced over the plant PA System.

Due to instrument 1EEBCR9100 being out of service, the National Weather Service was

called and reported wind speed to be constant at 5 MPH.

Wind direction was 85 degrees from North.

Containment radiation levels are remaining normal (4Whr)

The OSM directs you to classify the event per RP/O/A/5700/000 (Classification of

Emergency) AND complete the WCCSRO Immediate and Subsequent Actions enclosure of

the applicable Response Procedure.

i/ JPM OVERALL STANDARD: The Initial Notification form is completed with the appropriate

Protective Action Recommendations.

NOTES: This JPM is intended to be used with a blank "Emergency Notification Form"

provided to the candidate. Also provide the student with a complete copy of

RP/O/A/5700/004 General Emergency.

KA 194 001 A1.16

SRO Admin A 4 JPM

PAGE 3 OF 7

STEPS ELEMENTS STANDARD COMMENT:

REQUIRED

FOR UNSAT

1 Candidate implements Event was classified as a

procedure for General General Emergency.

Emergency.

After event classified, log

the Time Critical

Start Time

2 The Operations Shift Operator determines

Manager or delegate From initial conditions that

SHALL ANNOUNCE the this has already been

event over the plant P.A. performed.

system by performing the

following:

3 Complete items 1 - 10, Same

15 and 16 on Enclosure

4.1 - Emergency

Notification Form in

accordance with

Enclosure 4.3, section 1

4 COMPLETION OF THE

EMERGENCY

NOTIFICATION FORM

Complete Enclosure 4.1- Same

Emergency Notification

Form as follows:

Check A for Drill B for Operator checks B for

Emergency emergency

AND

Check INITIAL Same

AND

i/ * DENOTES CRITICAL

\

SRO Admin A 4 JPM

PAGE4OF 7

ii -

STEPS ELEMENTS STANDARD s/u COMMENT$

REQUIRED

FOR UNSAT

Continued.. .

Write in message 3perator writes message

4 number. lumber 1

Write in the unit(s) 3perator writes in Unit 1

AND

Communicators name 3perator writes

ommunicators name

4 Write in the transmittal 3perator will not enter a

ii time AND date :ime and date since

ie/she will not actually be

naking the transmission

Write in the appropriate 3perator will not enter a

number AND code word number and code word

- Since he/she will not

actually be making the

transmission

4 Continued

Same

Checks D for GENERAL

EMERGENCY

DENOT 3 CRITICAL

SRO Admin A 4 JPM

PAGE5OF 7

- ~

STEPS ELEMENTS STANDARD SIU COMMENT!

REQUIRED

FOR UNSAT

Sheck A for Emergency Same

Ieclaration At:

-

AND

ilVrite the time AND date Same

he classification is

jeclared: NOTE: The Declaration

Time of 0600 and Date of

D600 on MARCH 31*'. January 31*' is entered in

space provided.

Write the reason for Same

declaring the

classification

Check C for the Stable or Degrading

appropriate plant

condition

Check A SHUTDOWN Same

&NJ

write the time and date of Reactor Shutdown:

Reactor Shutdown Time: -0545-

Date: -03131103-

-

Check B AND write in the NIA

Reactor Power level

~

DENOT 5 CRITICAL

SRO Admin A 4 JPM

PAGE6OF 7

iTEPS ELEMENTS STANDARD COMMENT:

REQUIRED

FOR UNSAT

Check C . a release is Operator checks that a

occurring due to the SG release is occurring due

Tube Leak. to the SG Tube Leak.

Step # I 4 is not required If Step # I 4 is completed,

but can be filled in with it should be filled in with:

appropriate data. Wind Direction of 85 deg

from North and Wind

Speed of 5 mph.

Check B & C , Same

EVACUATE & SHELTER

IN-PLACE.

Also fills in appropriate Fills in zones for

zones.

Evacuate:

L,B,M,C,N,A,D,O,R.

Shelter:

E, F, G, H, I, J, K, P, Q, S

4 Continued

Cue:

Have the Emergency The Emergency

Coordinator approve the Coordinator, John Doe,

message just approved the

AND message. Please enter

time and date for the

present.

Write in the time AND Same

date the message was

approved

DENOTES CRITICAL

SRO Admin A 4 JPM

PAGE 7 OF 7

STEPS ELEMENTS STANDARD SIU COMMENT!

REQUIRED

FOR UNSAT

5 Make initial notification to NOTE: This step

State and County signifies the end of the

authorities using the Time Critical portion of

Emergency Notification this JPM. Enter the stop

Form in accordance with time below

Enclosure 4.3, section 2.

Cue: Another operator

Go to step 2.4 as soon will make the

as possible transmission the State

and Counties.

Stop Time

L/ * DENOTES CRITICAL

INITIAL CONDITIONS

Assume: Todav is Monday. It is now 0600 on MARCH 31*'

At 0545, the Reactor on Unit # I was tripped and Safety Injection initiated due decreasing

inventory and pressure.

A SGTR has occurred with an unisolable secondary line break on I C S/G inside containment.

All CA pumps have just tripped off and due to inadequate S/G levels, a valid Heat Sink Red

Path is in effect.

The event has been announced over the plant PA System.

Due to instrument 1EEBCR9100 being out of service, the National Weather Service was

called and reported wind speed to be constant at 5 MPH.

Wind direction was 85 degrees from North.

Containment radiation levels are remaining normal (6 R/hr)

ii The OSM directs you to classify the event per RP/O/A/5700/000 (Classification of

Emergency) @ l

completeJthe WCCSRO Immediate and Subsequent Actions enclosure of

the applicable Response Procedure.

. Duke Power Company

PROCEDUREPROCESSRECORD

(1) ID No. RP/O/N5700/004

Revision No. 01 7

-

b

PREPARATION

(2) Station McGuire Nuclear Station

(3) Procedure Tine General Emergency

/

(4) Prepared By LG4k Date 7-3-02

(5) Requires NSD ility Determination?

Yes (New procedureor revision with major changes)

0 No (Revisionwith minor changes)

rate previously pprovedchanges)

(6) Reviewed By- (OR) - Date ?/t+/o,

Cross-Dis?iplina eview By Date 2/2v,/6 L

Reactivity Mgmt. Review By . (OR) NA Date ? ) 2 . r / o t

Mgmt. Involvement Review By

ReviewedBy

(0ps.Supt.) NA

&-Date .z/zv!a L

.__ -

Reviewed By -. Date

(8) Temporary Approval (ifnecessary)

BY - _. (OSM/QR) Date

k (OR) Date

BY __.._ -

6 (9) Approved By Date/d- /-JX

PERFORMANCE 14 calendar days while work is being performed.)

(10) Compared with Control Copy ~~.~ ~- ~

Date

Compared with Control COPY ~~~~ ~~ ~.. ____ Date

Compared Wittr-ControlCOPY .... _ _ ~ ~~ Date -.___

(11) Date(s)Performed .. - ___ .-

Work Order Number (WO#) ~- __ -

COMPLETION

(12) Procedure Completion Verification

0Yes 0 N/A Check lists and/or blanks initialed. signed, dated or filled in NA. as appropriate?

0 Yes 0 N/A Requiredenclosures attached?

0 Yes 0 N/A Data sheets attached, completed, dated and signed?

0 Yes 0N/A Charts. graphs. etc. attached. dated. identified, and marked?

0 Yes N/A Procedure requirements met?

Verified By ~~~ ~~~~. .~~~~ .~ , ~~ ~ . . ~_ ~ _ Date -.

Procedure Completion Approved ... ~~ ~ ~ Date ~

'(14)

I Remarks (anach additionalpages, if necessary)

h

W

Duke Power Company Procedure No. I

McGuire Nuclear Station RPi~fN5700l004

General Emergency

Reference Use

MC0048M7 J

h RP/O/A/5700/004

L/ Page 2 of 5

General Emergency

1. Symptoms

Events are in process or have occurred which involve actual or imminent substantial core

degradation or melting with potential for loss of containment integrity.

2. Immediate Actions

7

NOTE: The Immediate Actions and part of the Subsequent Actions have been separated into

position specific enclosures to enhance timely completion and consistent execution.

.

h R P/o/A/57oO/OO4

Page 3 of 5

L,

3. Subsequent Actions

3.1 Follow-up Notifications

r ~

NOTE: -

IF changes to the initial Protective Action Recommendations are recognized and approved by

the Emergency Coordinator, these changes shall be. transmitted to the offsite agencies within

15 minutes. (PIP-M-00-02138)

__ 3.2 Ensure completion of Enclosure 4.7 (Emergency Coordinator / Emergency Operations

Facility Director Turnover Checklist) prior to turnover of Emergency Coordinator

responsibilities.

NOTE: A TSC preprogrammed fax button is available on the Control Room fax machine.

-

IF changes to the initial Protective Action Recommendations are recognized during the

turnover, the turnover should not be. completed until the Control Room transmits this

notification to the offsite agencies. (PIF'-M-0-00541]

3.3 WHEN TSC Emergency Coordinator is ready to receive turnover THEN perform one of the

following to facilitate turnover:

__ Hand deliver turnover sheet to the TSC Emergency Coordinator.

-

__ Fax turnover sheet to the TSC

-3.4 In the event that a worker's behavior or actions contributed to an actual or potential

. . substantial degradation of the level of safety of the plant (incidents resulting in an Alert or

I higher emergency declaration), the supervisor must consider and establish whether or not a

L.

for cause druglalcohol screen is required. The FFD Program Administrator or designee is

available to discusslassist with the incident.

3.5 Protective Actions Onsite

~- 3.5.1 Evacuate non-essential personnel from the site after all personnel have been

accounted for via Site Assembly. Refer to RP/O/A/5700/01 I (Conducting a Site

Assembly. Site Evacuation or Containment Evacuation).

__ 3.5.2 E a situation which is immediately hazardous to life or valuable property exists,

THEN evaluate potential dose rates by one of the following methods:

a. Contact RP Shift at Ext. 4282

b. Assess area monitors

__ 3.5.3 Complete Enclosure 4.8 (Request for Emergency Exposure), prior to dispatch of

emergency workers if emergency situation precludes documentation.

h

RP/O/A/5700/004

Page 5 of 5

'u

3.6 Using Section D of the Emergency Plan (EAL Basis), assess the emergency condition:

__ 3.6.1 Remain in a General Emergency,

-

-3.6.2 Terminate the emergency. REFER TO RP/O/A/5700/012 (Activation of the

Technical Support Center (TSC)), Enclosure 4.19 for termination criteria.

3.7 Termination Notifications

NOTE Enclosure 4.6 has instructions for completion and transmission of termination notifications.

__ 3.7.1 Complete Enclosure 4.1 (Emergency Notification Form) in accordance with

Enclosure 4.6, Section 1.

- 3.7.2 Make termination notification to State and County authorities using the

Emergency Notification Form in accordance with Enclosure 4.6, Section 2.

4. Enclosures

4. I Emergency Notification Form.

4.2 Guidance for Offsite Protective Actions

4.3 Initial Notification Completionflransmission

4.4 NRC Event Notification Worksheet

4.5 Follow-up Notification Completionflransmission

4.6 Termination Notification Completion/Transmission

4.1 Emergency Coordinator / Emergency Operations Facility Director Turnover Checklist

4.8 Request for Emergency Exposure

4.9 OSM Immediate and Subsequent Actions ( P P O-M97-4638}

4. IO WCC SRO Immediate and Subsequent Actions (PIP O-M97-4638}

l

i,

-

4.11 STA Immediate and Subsequent Actions (PIP O-M97-4638}

Enclosure 4.1

-\ ... EMERGENCY NOTIFICATION Page 1 of z

i/ .IS IS A DRILL ACTUAL EMERGENCY OINITIAL FOLLOW-UP MESSAGE NUMBER

I tTE: McGuire Nuclear Sile UNIT: REPORTED BY:

3. TRANSMITTAL TIMUDATE: -1 I- C0NFIRMATH)NPHONE NUMBER (704) 875-6044

%lua#l - 7 d - n

4. AUTHENTICATION (I1 Required):

INUmbrO lcodmd)

5. EMERGENCY CUISSIFICATION:

NOTlFlCAllON OF UNUSUAL M N T BALERT USlTEM EA EMERGENCY @GENERAL EMERGENCY

6. @Emergency Odaration A:I @Termination A:I TIMEIDATE: I-(IfB,poloilem16.)

I

7. EMERGENCY DESCRIPTION/REMARKS:

8. PLANT CONDITION: IMPROVING BSTABLE ~JDEGRADING

9. REACTOR STATUS: aSHUTDOWN: TIMUDATE: -1 I- m-%POWER

I*surn1 m ?s II

10. EMERGENCY RELEASE(S):

a N O N E (Go lo ilem 14.) H P O T E M I A L (GO TO ITEM 14.) B l S OCCURRING m H A S OCCURRED

-w. TYPE OFRELEASE: OELEVATEO ~GROUNO LEVEL

gAIRBORNE Slarled: I*(Eirranl -I-ml-- Stopped: Tun! lunrn) -1-1-

L&:I'

@LIOUIO: Slarled: T iItlsran) -l-i?x-'- Slopped: ImltllM) -1-1-

.1 .

w .RELEASE MAGNITUDE: CURIES PER SEC. OCURIES NORMALOPERATING LIMITS: BELOW DABOVE

@NOBLE GASES ~IODINES

QPARTICUIATES OTHER

"13. ESTIMATE OF PROJECTEO OFFSlTE DOSE:

-.

ONEW DUNCHANGED PROJECTION TIME

IEaSle,")

.

TEDE Thyroid COE

mrem mrem ESTIMATED DURATION: HAS.

SITE BOUNDARY

2 MILES

5 MILES

10 MILES

15. RECOMMENDED PROTECTIVEACTIONS:

HNO RECOMMENDED PROTECTIVEACTIONS

EVACUATE

QSHELTER IN-PLACE

aOlHER -

.. lnformalion

I1 iiems 8-14 have no1 changed, only items 1-7 and 15-16 are required to be completed.

may no1 be available on inilial nolilicalions.

Enclosure 4.1 RP/O/A/s 700/004

R Page 2 of 2

-

GOVERNMENT AGENCIES NOTIFIED

1.

(Mme)

.

NCSlaIe I

Idale) (bme) EOC W. Sg. 314

EOC 8el Line (919) 753.3943

3.

7name)

Gaston County

?dale) (QW)

(awcy)WP Sel. si. 112

W P B e n h e C104)8663300

4.

(Mme)

Lincoln County

-ale) (Qrn) WP Sel. Sg. 113

WP Ben line (704)n58m

5.

?name)

lredell County

7dale) (IW) WP Sel. Sg. 114

-- WP Bel Ine (704)8783039

7.

Fame)

Enclosure 4.2

Guidance for Off-site Protective Actions

Emergency

Declared

Recommend evacuation of

2 mile radius & 5 miles

downwind. Recommend in-place

shelter for all zones not evacuated

out to 10 miles

(See Enclosure 4.2. page 3 O f 4)

Yks

URGENT

Evacuate zones L, B, M, C. N. A, D, 0, R

Shelter zones E, F, G, H, I, J, K,P,Q,S

I

L&

,c

i

Large fission product

inventory greater than No

Containment?

(See Enclosure 4.2, page 2

projected by RP to

exceed Protective

Action Guides?

Recommend evacuation of 5 mile radius &

10 miles downwind. Recommend in-place

shelter for all zones not evacuated out to Recommend protective

10 miles. actions in accordance with

the Protective Action Guides,

(See Enclosure 4.2, page 2 of 4)

u,

Enclosure 4.2 RP/O/A/5700/~

Guidance for Off-site Protective Actions Page 2 of 4

._ Enclosure 4.2 RP/O/A/5700/004

i/ Guidance for Off-site Protective Actions Page 3 of 4

Protective Action Zones Determination

GUIDANCE FOR OFFSITE PROTECTIVE ACTIONS

PAGs

i Dose) -

Total Effeetive Committed Dose

Dose Equivalent Equivalent (CDE)

Thyroid Recommendation

< 5 rem No Protective Action is required based on

nroiected dose.

I -> I rem -

> 5 rem Evacuate affected zones and shelter the

remainder of the 10 mile EPZ not evacuated.

Protective Action Guides (PAGs) are levels of radiation dose at which prompt protective actions should

be initiated and are based on EPA-400-R-92-001, Manual of Protective Action Guides and Protective

Actions for Nuclear Incidents.

Enclosure 4.2

-\ RP/O/A/5700/004

Guidance for Off-site Protective Actions Page 4 of 4

c.

McGUIRE PROTECTIVE ACTION ZONES

(2 and 5 mile radius, inner circles)

10 MILE EPZ

Enclosure 4.3 RP/O/A/5700/004

Initial Notification Page 1 of 9

Completioflransmission

1. Completion of the Emergency Notification Form

NOTE: ONLy Items 1 - 10, 15 and 16 are required.

Items 11 - 14 may be skipped. I

1. I Complete Enclosure 4.1 (Emergency Notification Form) as follows:

NOTE: Message # s should be sequentially numbered throughout the drilllemergency.

__ Item 1 Check A for Drill O R B for Actual Emergency AND

Clieck INITIAL AND

Write in filessage number.

NOTE: Certain events could occur at the plant site such that both units are affected. These may include:

Enclosure 4.3 (Abnormal Rad Levels/Radiological Effluent), Enclosure 4.6 (FiresExplosions and

Security Events) and Enclosure 4.7 (Natural Disasters, Hazards and Other Conditions Affecting Plant

Safety) from RP/O/A/5700/000, (Classification of Emergency). Consider this when completing the

L.

.=1 <, unit designation on line 2 of the Emergency Notification Form. (PIP 0-M97-4638

!.

REPORTED BY: is the Communicatorsname.

t

__ Item 2 Write in the unit(s) AND Communicators name.

NOTE: Information

Form. -

-.

for Items 3 and 4 will be completed during transmission of the Emergency Notification

I

Item 3 Write in the transmittal time AND date.

__ Item 4 Write in appropriate number AND codeword.

__ Item 5 Check D for GENERAL EMERGENCY.

__ Item 6 Check A for Emergency Declaration At: AND

Write the time AND date the classification was declared.

Enclosure 4.3 RP/O/A/5700/004

Initial Notification Page 2 of 9

Completioflransmission

I

NOTE: Reference RP/O/A/5700/000, (Classification of Emergency) I

I

Item 7 Enter EAL Number and Emergency Description of the reason for declaring the emergency

classification (in layman's terms, if possible). DO NOT use system abbreviations,

acronyms or jargon which may cause confusion. Instead, write out the description in long

hand. Be sensitive to the fact that certain descriptive technical terms may elicit

unanticipated reactions from others. {PIPO-M98-2065)

Item 8 Check the appropriate plant condition. {PIPO-M97-4210 NRC-I)

. A Improving: Emergency conditions are improving in the direction of a

lower classification or termination of the event.

.B Stable: The emergency situation is under control. Emergency core

cooling systems. equipment, plans, etc., are operating as designed.

.C Degrading: Given current and projected plant conditiondequipment status, recovery

% efforts are not expected to prevent entry into a higher emergency classification or the

need to upgrade offsite Protective Action Recommendations.

__ Item 9 Check A SHUTDOWN AND write the time and date of Reactor Shutdown

-

Check B AND write in the Reactor Power level.

Enclosure 4.3

Initial Notification Page 3 of 9

Completioflransmission

~~

NOTE: 1. An emergency release is any unplanned, quantifiable discharge to the environment

associated with a declared emergency event. (This definition is based on an NRC commitment

made on 11/30/90 following McGuireS Steam Generator Tube Rupture.) (PIP O-M97-4256)

2. Notify the OSM if box C or box D is checked.

3. Base the determination of emergency release on:

EMF readings,

e containment pressure and other indications,

field monitoring results,

knowledge of the event and its impact on systems operation and resultant release ~2:;;s.

4. An emergency release is occurring if any one or more of the following bulleted conditions arc

met associated with a declared emergency:

e Either containment particulate, gaseous, iodine monitor (EMFs 38,39 and/or 40) readings

indicate an increase in activity,

Containment monitor (EMFs 5 1A and/or 5 IB) readings indicate greater than 1 SWhr,

-

AND

Either containment pressure is greater than 0.3 psig,

-

An actual containment breach is known to exist.

Unit vent particulate, gaseous, iodine monitor (EMFs 35.36, and/or 37) readings indicate an

increase in activity.

-

Condenser air ejector exhaust monitor (EMF 33) or other alternate means indicate Steam

Generator tube leakage.

Confirmed activity in the environment reported by Field Monitoring Team(s).

Knowledge of the event and its impact on systems operation and resultant release paths.

___ Item 10 Check the appropriate box for emergency release.

A NONE: clearly no emergency release is occumng or has occurred.

B POTENTIAL: discretionary option for the EC or EOFD.

C IS OCCURRING: meets the specified conditions.

D HAS OCCURRED: previously met the specified conditions.

Enclosure 4.3 RP/O/A/5700/004

Initial Notification Page 4 of 9

Completioflransmission

- Item 15 Check B A N D write affected zones for evacuation

-

AND

Check C AND write the letter designation for all other zones not evacuated

__ Item 16 Have the Emergency Coordinator approve the message AND

Write in the time m d a t e the message was approved.

2. TRANSMISSION OF THE EMERGENCY NOTIFICATION FORM

~~ ~~ -

NOTE: 1. All initial notifications are verbal. Avoid using abbreviations or jargon likely to be unfamiliar to

the State and Counties. If any information is not available or not applicable, write out "Not

Available" or "Not Applicable" in the margin or other space as appropriate. Do not abbreviate

"N.A.".

2. The backup means of communications are the Bell line or County Emergency Response Radio.

RP/O/N5700/014, Enclosure 4.1 is available for needed backup numbers.

I 3. Refer to page 6 of 9 of this Enclosure for instructions on how to use the County Emergency

Response Radio if selective signaling or Bell line is not available.

~ 2.3 As the Stale and Counties answer, check them off on the back of the notification form. At least one

attempt using the individual selective signaling code must be made for any missing agencies, Proceed

with the notification promptly following an attempt to get missing agencies on the line.

__ 2.4 Check the State and Counties are on the line, document this ti-ne in item #3 on the form, This time

should not exceed 15 minutes from the time of declaration (Item # 6).

~ 2.5 Tell them you have an emergency notification from the McGuire Control Room and to get out the

Emergency Notification Form.

- 2.6 Read the complete message slowly. line by line, beginning with Item # I , allowing ample time to

COPY.

Enclosure 4.3

Initial Notification Page 5 of 9

Completioflransmission

NOTE:

- 2.7

Refer to page 7 of 9 of this enclosure for the authentication codeword list.

When you reach item #4, ask the State or a County to authenticate the message. The agencyshould

I

give you a number and you should provide the appropriate codeword. Write the number and

codeword on the form.

-2.8 After communicating the initial message, ask if there are any questions. Record individuals names

and times on the back of the form. This time is the same time as Item #3.

__ 2.9 After verbally transmitting the message, FAX a copy (front page only) to the agencies. Refer to pages

8 of 9 and 9 of 9 of this Enclosure for FAX operation.

-2.10 Continuous attempts to contact missing agencies must be made i f unable to complete the notification

per step 2.3. Document the time these agencies were contacted on the back of the notification form.

Enclosure 4.3

RPfOfAJS7001004

.. Initial Notification Page 6 of 9

ii Completioflransmission

NOTE: This radio will only contact the County warning points. The State cannOt be contacted on this radio.

Have one of the Counties relay the message to the State.

<

Enclosure 4.3

RP/O/A/5700/004

-\

Initial Notification Page 7 of 9

ii Completioflransmision

AUTHENTICATION CODEWORD LIST

This page is left intentionally blank.

Enclosure 4.3

RPi~iA/5700lW4

Initial Notification Page 8 of 9

CompletiowTransmission

OPERATION OF THE FAX

A. GROUPFAX

NOTE: 1, The FAX will dial each agency in sequence. If the FAX is busy, it will try again after completing

the other calls.

2. This sends a FAX to all County Warning Points, State EOC, TSC, EOF, News Group and JIC.

__ I . Insert the Emergency Notification Form face down into the FAX.

- 2. Press GROUP FAX button.

I _ 3 . Press "SEND/RECEIVE" button.

B. INDIVIDUAL FAX

- 1 Insert the Emergency Notification Form face down into the FAX.

Select location(s) to receive the fax:

b Press News Group.

b Press TSC.

Press State of North Carolina EOC.

-- Press Mecklenhurg County Warning Point.

. Press Gasron County Warning Point.

4 Press Lincoln County Warning Point.

b Press lredell County Warning Point.

. Press Catawba County Warning Point.

Press Cabarms County Warning Point.

Press EOF.

. Press JIC.

-

WHEN the appropriate individual location is sclccted, -

THEN press the "SENDRECEIVE'

button.

Enclosure 4.3 RP/O/A/57001004

Initial Notification Page 9 of 9

Completioflransmission

~

NOTE: RP/OlA/5700/014, Enclosure 4.1 is available for needed manual FAX numbers.

I

C. To send a FAX to a location dialing manually:

__ I . Insert the document face down into the FAX.

__ 2 . Using the keypad, dial the number that you wish to call

__ 3. Press "SENDIRECEIVE"button

e

.. Enclosure 4.4 RPlol~l57Ool0o4

bI6 I c THIS IS THE McGUlRE NUCLEAR S K E I NRC Event

N NRCREGION Notification

2 MAKLNG WorksheetREPORT Page 1 of 2

A N EVENTNOTIFICATION

IFICATION uNm CALLERS NAME CALLBACK TELEPHONE b N R C O P E R A n O N S O ~ C E coNrACTED

R

.A W D A T E ENSL704)-8756044

OT 1-888-270-0173

EVENTTIME & R ZONE

e q m I1 EVENT DATE POWERIMODE B E W R E

,.. .

NOTIFICATIONS YES No ANYTHING UNUSUALOR N O T U N D E R S W D ? 0 YES 0 NO

BE

NRC RESIDENT (Explain above)

STATE(r) ALL SYSTEMS FUNCTION AS YES 0 0 NO

REQUIRED

A I

IQUID RELEASE ASEOUS RELEASE NPLANNED RELEASE LANNED RELEASE

I FS EXCEEDED NGOINC I I "REAS

RMINATED

ONmRED

1 P NMONmRED FFSm RELEASE M ALARMS EVACUAED

I

I I 1 I

OTE: Contact R i d n i m Fmccl!on Shift Io obtam the lulloweng ~nlwmatton

-

IF the notification is due and the information is nM available,

-

T H E N mrt "Not Available" and cmplete the ndification.

,

C S OR SG N D E LEAKS.

I

-GATION O F M E LEAK (e.g SF#.valve. pipe. etc.):

I I I

CHECK OR flLL P4 APPLICABLE m h l S (specific detmlj/crpbnauonr thmld bccosnd m cwnt dacnption) I

LEAK R A T E gpdgpd .S. LtMm EXCEEDED UDDEN OK LONG TERM DEVELOPMENT

-EAK START D A T E TIME: O O U N T ACI'IVm: PRIMARY SECONDARY

-

-. Last Sample) Xe e o r n C i / m l Xe eq__mCiJrnl

lcdinc eq. pmCiJml lcdinc cq. _mCi/mi

IST OFSAFETY RELATED EQUIPMENT NOTOPERATIONAL

Enclosure 4.5

RP/O/A/5700/004

Follow-Up Notification Page 1 of 6

Completionrammission

1. Completion of the Emergency Notification Form

NOTE: If items 8 - 14 have not changed from the previous message, only items 1 - 7.15 and 16 are

required to be completed. Avoid using abbreviations or jargon likely to be unfamiliar to the State

and Counties. If any information is not available or not applicable, write out "Not Available" or

"Not Applicable" in the margin or other space as appropriate. Do not abbreviate "N.A.".

1.1 Complete Enclosure 4.1 (Emergency Notification Form as follows):

NOTE: Message # s should be sequentially numbered throughout the drill/emergency.

1

__ Item 1 Check A for Drill B for Actual Emergency AND

Check FOLLOW-UP AND

Write in message number.

NOTE Certain events could occur at the plant site such that both units are affected. These may include:

Enclosure 4.3 (Abnormal Rad L.evels/RadiologicalEffluent), Enclosure 4.6(FiresExplosions and

Security Events) and Enclosure 4.7 (Natural Disasters, Hazards and Other Conditions Affecting

\V>,

Plant Safety) from RP/O/A/5700/000, (Classification of Emergency). Consider this when

completing the "unit designation" on line 2 of the Emergency Notification Form. (PIP 0-M97-

4638)

REPORTED BY: is the Communicator's name.

- Item 2 -~

- Write in the unit(s) ANDCommunicator's name

NOTE: Transmittal time is the time you FAX the form to the agencies.

__ Item 3 Write in the transmittal time W d a t e

__ Item 4 Authentication is not required when faxing

__ Item 5 Check D for GENERAL EMERGENCY

__ Item 6 Check A for Emergency Declaration At: AND

Write the time AND date the classification was declared.

-.>

Enclosure 4.5 R P/~/N57OO/OO4

Follow-Up Notification Page 2 of 6

L.

Cornpletioflransmission

[NOTE: Reference RP/O/A/5700/000, (Classification of Emergency) I

__ Item 7 Enter EAL Number and Emergency Description of the reason for declaring the

emergency classification (in layman's terms, if possible). DO NOT use system

abbreviations, acronyms or jargon which may cause confusion. Instead, write out

the description in long hand. Be sensitive to the fact that certain descriptive

technical terms may elicit unanticipated reactions from others. (PIP O-M98-2065)

In addition, provide a description of changes in plant conditions since the last notification. Items to be

considered for inclusion are as follows: (PIP 0-M98-2065)

Other unrelated classifiable events (for example, during an Alert, an event which, by itself would

meet the conditions for an Unusual Event)

MajodKey Equipment Out of Service

Emergency response actions underway

Fire(s) onsite

Flooding related to the emergency

Explosions

L&; Loss of Offsite Power

. CoreUncovery

CoreDamage

Medical Emergency Response Team activation related to the emergency

Personnel injury related to the emergency or death

Transport of injured individuals offsite - specify whether contaminated or not

Site Evacuation/relocationof site personnel

Saboteurs/Inrruders/Suspicious deviceflhreats

Chemical or Hazardous Material Spills or Releases

Extraordinary noises audible offsite

Any event causinghequiring offsite agency response

Any event causing increased media attention

Remember to "close the loop" on items from previous notifications

Enclosure 4.5 RP/O/A/57001004

Follow-Up Notification Page 3 of 6

Completioflransmission

- Item 8 Check the appropriate plant condition. (PIP M-097-4210 NRC-1)

.A. Improving: Emergencyconditionsare improving in the direction of a

lower classification or termination of the event.

.B. Stable: The emergency situation is under control. Emergency core

cooling systems, equipment, plans, etc., are operating as designed.

C. Degrading: Given current and projected plant conditions/equipment status,

recovery efforts are not expected to prevent entry into a higher emergency

classification or the need to upgrade offsite Protective Action

Recommendations.

__ Item 9 Check A SHUTDOWN AND write the time and date of Reactor Shutdown

-

Check B AND write in the Reactor Power level.

Enclosure 4.5 RP/O/A/5700/004

Follow-Up Notification Page 4 of 6

Completioflransmission

HOTE: 1. An emergency release is any unplanned, quantifiable discharge to the environment

associated with a declared emergency event. (This definition is based on an NRC

commitment made on 11/30/90 following McGuire's Steam Generator Tube Rupture.) {PIP0-

M97-4256)

2. Notify the OSM if box C or box D is checked.

3. Base the determination of emergency release on:

EMF readings,

containment pressure and other indications,

field monitoring results,

knowledge of the event and Its impact on systems operation and resultant release paths.

4. An emergency release is occurring if any one or more of the following bulleted condition

are met associated with a declared emergency:

0 &r containment particulate. gaseous, iodine monitor (EMFs 38.39 andlor 40) reading:

indicate an increase in activity,

-

Containment monitor (EMFs 51A and/or 51B) readings indicate greater than ISWhr,

A? -

AND

-containment pressure is greater than 0.3 psig,

-

An actual containment breach is known to exist

Unit vent particulate, gaseous, iodine monitor (EMFs 35, 36. andor 37) readings indicate

an increase in activity.

Condenser air ejector exhaust monitor (EMF 33) or other alternate means indicate Steam

Generator tube leakage.

Confirmed activity in the environment reported by Field Monitoring Team(s)

Knowledge of the event and 115 impact on systems operation and resultant release paths.

__ Item 10 Check the appropriate box for emergency release.

A NONE: clearly no emergency release is occurring or has occurred.

B POTENTIAL: discretionary option for the EC or EOFD.

C IS OCCURRING: meets the specified conditions.

D HAS OCCURRED: previously met the specified conditions.

Enclosure 4.5 RP/&N57001004

Follow-Up Notification Page 5 of 6

CompletiodIransmission

- I .2 -

.-llow-up notification is due and information for Items - through 14 cannot be obtained from

RP shift, THEN mark each item Not Available and go to Item 15.

__ Item 11 Check GROUND LEVEL AND

Check A for AIRBORNE B for LIQm AND

Write in the time AM)date the release started- stopped if available.

- Item 12 Check CURIES PER SECOND AND

Check BELOW ABOVE normal operating limits AND

Check the appropriate blocks A, B. C, D AND write in the value(s).

NOTE: If unchanged from the previous notification, the information does not have to be repeated.

1

__ Item 13 Check NEW UNCHANGED AND

Write in the projection time AND

Write in the estimated duration AND

Write in the TEDE and Thyroid CDE values.

- Item 14 Check A, B, C, D& provide values for each.

bg;

__ Item I 5 Check B AND write affected zones for evacuation

Check C AND write the letter designation for all other zones not evacuated

__ Item 16 Have the Emergency Coordinator approve the message AND

- Write in the time AND date the message was approved.

Enclosure 4.5

~~iOi~15700iw

Follow-Up Notification Page 6 of 6

Completioflransmission

2. 'Ikansmission of the Emergency Notification Form

-

i~

I

NOTE: For routine, follow-up notifications, FAX a copy of the notification form instead of verbally

transmitting the message (front page only). This applies only if the message does not involve a

change in the emergency classification or the protective action recommendations or a termination

! of the emergency. Call each agency to verify they received the message.

Enclosure 4.6

RP/O/A/5700/004

Termination Notification Page 1 of 6

Completioflransmission

1. Completion of the Emergency Notification Form

NOTE: A termination message should be marked as FOLLOW-UP on the Emergency Notification Form.

I

1.1 Complete Enclosure 4.1 (Emergency Notification Form) as follows:

__ Item I Check A for Drill B for Actual Emergency

Check FOLLOW-UP AND

Write in message number.

I

NOTE: Certain events could occur at the plant site such that both units are affected. These may include:

Enclosure 4.3 (Abnormal Rad Levels/Radiological Effluent), Enclosure 4.6 (FiresExplosions and

Security Events) and Enclosure 4.7 (Natural Disasters, Hazards and Other Conditions Affecting

Plant Safety) from RP/O/A/5700/000, (Classification of Emergency). Consider this when

completing-the unit designation on line 2 of the EmergencyNot/fication Form. {PP0-M97.

4638)

I REPORTED BY: is the Communicators name.

<;\ __ Item 2 Wnte in the unit(s) AND Communicators name.

NOTE: Information for Items 3 and4 will be completed during transmission of the Emergency Notification

Form.

__ Item 3, Write i n the transmittal time AND date

__ Item 1 Write in appropriate number AND codeword.

__ Itern 5 Check D for GENERAL EMERGENCY

__ Item 6 Check B forTermination At: AND

Write the time AND date the classification was terminated.

-Item 16 Have the Emergency Coordinator approve the message AND

Write in the time m d a t e the message was approved.

Enclosure 4.6

RPlO/A/5700/004

Termination Notification Page 2 of 6

Completioflransmission

2. Transmission of the Emergency Notification Form

NOTE: 1. All termination notifications are verbal. Avoid using abbreviations orjargon likely to

unfamiliar to the State and Counties. If any information is not available or not applicable, write

out "Not Available" or "Not Applicable" in the margin or other space as appropriate. Do not

abbreviate "N.A.".

2. The backup means of communications are the Bell line or County Emergency Response Radio.

RP/O/A/5700/014, Enclosure 4.1 is available for needed backup numbers.

3. Refer to page 3 of 6 of this enclosure for instructions on how to use the County Emergency

Response Radio if selective signaling or Bell line is not available.

__ 2.1 Use the Selective Signal telephone by dialing * I and depressing the push to talk button.

- 2.2 -IF Selective Signaling Group Call fails, THEN go to RP/O/A/5700/014, Enclosure 4.1 for manual

selective signaling numbers.

As the State and Counties answer, check them off on the back of the notification form. AI least

one attempt using the individual selective signaling code must be made for any missing agencies.

t Proceed with the notification promptly following an attempt to get missing agencies on the

line.

__ 2.4 Check the State and Counties are on the line, document this time in item #3 on the form.

__ 2.5 Tell them you have an emergency notification from the McGuire Control Room and to get out the

Emergency Notification Form.

__ 2.6 Read the complete message m,line by line, beginning with Item # 1, allowing ample time to

COPY.

NOTE: Refer to page 4 of 6 of this Enclosure for the authentication codeword list.

__ 2..7 When you reach item #4, ask the State or a County to authenticate the message. The agency

should give you a number and you should provide the appropriate codeword. Write the number

and codeword on the form.

__ 2.8 After communicating the message, ask if there are any questions. Record individuals' names and

times on the back of the form. This time is the same time as Item #3.

-'

i

- 2.9 After verbally transmitting the message, FAX a copy (front pdge only) 10the agencies. Refer to

page 5 of 6 and 6 of 6 of this enclosure for FAX operation.

\ .-

Enclosure 4.6 RP/O/Af5700/004

Termination Notification Page 3 of 6

Completion/Transmission

- 2.10 Continuous attempts to contact missing agencies must be made if unable to complete the

notification per step 2.3. Document the time these agencies were contacted on the back of the

notification form.

COUNTY EMERGENCY RESPONSE RADIO

NOTE: This radio will only contact the County warning points. The State cannOt be contacted on this

radio. Have one of the Counties relay the message to the State.

Group Call:

~ 1. Press 20 to activate all County radio units

__ 2. When the ready light comes on, press the bar on the transmitter microphone and say:

"This is McGuire Control Room to all Counties, do you copy?"

Once all Counties respond, begin transmitting the message using step 2.3 through 2.10 of this

enclosure.

Wf' Proceed with the notification promptly following an attempt to get missing

agencies on the air.

E:RP/O/A/5700/014, Enclosure 4.1 is available for needed individual radio codes.

~ 3. If a County fails to respond on the group call, press their individual code on the encoder and say:

-.

"This is McCuire Control Room to (Agency you are calling), do you copy?"

Once the County responds. begin transmitting the message using step 2.3 through step 2.10 of this

enclosure.

~ 4. After you have finished transmitting the message, concluue by saying:

"This is WQC700 base clear."

~ 5. Continuous attempts to contact missing agencies must be made if unable to complete the

notification per Step 2. Document the time these agencies were contacted on the back of the

notification form.

Enclosure 4.6 RP/O/A/5700/004

Termination Notification Page 4 of 6

Completioflransmission

AUTHENTICATION CODEWORD LIST

This page is left intentionally blank.

Enclosure 4.6

RP/O/N5700/004

I .

Termination Notification Page 5 of 6

U" Completioflransrnission

OPERATION OF THE FAX

A. GROUPFAX

NOTE: 1. The FAX will dial each agency in sequence. If the FAX is busy, it will try again after

completing the other calls.

2. This sends a FAX to all County Warning Points, State EOC, TSC, EOF, News Group and JIG.

__ 1. Insert the Emergency Notification Form face down into the FAX.

- 2. Press "GROUP F A X button.

__ 3. Press "SENDIRECEIVE"button.

B. INDIVIDUAL FAX

-1. Insert the Emergency Notification Form face down into the FAX.

2. Select location(s) to receive the fax:

Press News Group.

- . Press TSC.

Press State of North Carolina EOC.

Press Mecklenburg County Warning Point.

Press Gaston County Warning Point.

Press Lincoln County Warning Point.

Press Iredell County Warning Point.

Press Catawba County Warning Point.

. Press Cabarms County Warning Point.

Press EOF.

Press JIC.

L.k

-

__ 3. WHEN the appropnate individual Iocatlon I S selected, THEN press the "SENDIRECEIVE

button.

Enclosure 4.6

RP/O/A/5700/004

Termination Notification Page 6 of 6

Completiod'ransmission

OPERATION OF THE FAX

~

NOTE: RP/O/A/5700/014, Enclosure 4.1 is available for needed manual FAX numbers.

I

C. To send a FAX to as&& location dialing manually:

__ 1. Insert the document face down in the FAX.

__ 2. Using the keypad, dial the number that you wish to call.

-3. Press "SENDRECEIVE button.

Enclosure 4.7 RP/O/A/5700/004

Emergency Coordinator I Emergency Page 1 of 1

Operations Facility Director Turnover

Checklist

UNIT(S) AFFECTED ut u2

IPIP-M-99-38WI

POWER LEVEL NCSTEMP NCS PRESS

IATG:

u-1

'ME

U.2

NOUE DECLARED A T : TSC ACTIVATED AT

ALERT DECL,\RED A T EOF ACTIVATED A T

SAE DECLARED A T

G.E. DECLAREDAT

RE\SON FOR EhlER CLASS

YES NO TIME LOCATION OR COMMEhTS

SITE ,\SSEMBLY

SITE EVAC. (NON-ESSEN.)

SITE EVAC. (ESSENTIAL)

OTHER OFFSITE AGENCY

IWOLVEMENI'

MEDICAL

FIRE

POLICE

NUMBER NUhlBER

ASSEM. DEPLOYED

FIELD hlON. TE,\hlS

- ZONES ZONES

EVAC SHELTERED

PAW.

YES NO

RELEASE IN PROGRESS

RELEASE PATHWAY

CONTAMI\IENT PRESSURE PSlG

W I M ) DIRECTION WIND SPEED

NUMBER TIME

LAST MESSAGE SENT:

NEXT MESSAGE DUE:

N O W EOF COMhlUNIC,\TION CHECKS SHOULD BE COMPLETED PRIOR TO hCTIVhTING TIIE EOF

Enclosure 4.8

T- RPIOlN57001004

Request for Emergency Exposure (a) Page I of 1

i/

(a) Excludes declared pregnant women

(b) Includes skin and body extremities

(c) Only on a volunteer basis to persons fully aware of the risks involved. All factors

..

being equal, select volunteers above the age of 45 and those who normally

encounter little exposure.

-'&:

My signature indicates my acknowledgement that I have been informed that I may be exposed to the levels of

radiation indicated above. I have been fully briefed on the task to be accomplished and on the risks of this

exposure.

1. acknowledge this planned Emergency Exposure

(RPM or designee. signature or note of verbal authorization Datemime

1. approve this planned Emergency Exposure at

(Emergency Coordinator or EOF Director. signature or note of verbal authorization Datemime

Subsequent Radiation Protection Action:

- Determine need for medical evaluation

- Initiate reponing requirements per IOCFR20

-Copy to Individual's Exposure History File

Enclosure 4.9

~~~0/~/5700/004

OSM Immediate and Subsequent Actions Page 1 of 4

L

1. Immediate Actions

Initial

__ 1.1 The Operations Shift Manager or designee SHALL ANNOUNCE the event over the plant

P.A. system by performing the following:

1 .I. 1 Turn on the outside page speakers.

I NOTE: For drill purposes, state 'This is a drill. This is a drill."

Any plant phone in the Control Room horse shoe area or extension 4021 is programmed

to access 710, site all call. {PIPO-M98-2545)

.~ 1.1.2 Dial 710; pause, dial 80. Following the beep, announce "a General Emergency

has been declared". Provide a brief description of the event (may be written

below) and announce "Activate the TSC/OSC and E O F .

.'--.&?.

1.1.3 Repeat the preceding announcement one time.

~ I . I .4 Turn off the outside page speakers.

Enclosure 4.9 ~~iO1~15700im

P OSM Immediate and Subsequent Actions Page 2 of 4

NOTE: I. Initial notification to the State and Counties must be. made within 15 minutes of the

event declaration, using Enclosure 4.1.

2. Enclosure 4.3 has instructions for completion/transmission of the Emergency

- .

Notification Form

1.2 The Emergency Coordinator shall recommend to offsite authorities in the initial notification

the following:

NOTE: 1. To obtain the wind speed, use chart recorder lEEBCR9100, point #5 (Average Lower

Wind Speed).

2. To obtain the wind direction, use chart recorder lEEBCR9100, point 28 (Average Upper

Wind Direction).

3. If either point on 1EEBCR9100 is unavailable, obtain needed data from one of the

following sources in order of sequence:

A. DPC Meteorological Lab (8-594-0341)

B. National Weather Service in Greer, S.C. (864-879-1085 or 1-800-268-7785)

C. Catawba Nuclear Station Control Room (8-831-5345).

NOTE: Echanges to the initial Protective Action Recommendations are recognized and approved by

the Emergency Coordinator, these shall be transmitted to the offsite agencies within 15

minutes. (PIP-M-00-01238)

- 1.2. I Econtainment radiation levels exceed the levels on Enclosure 4.2, page 2 of 4,

Guidance for Determination of Gap Activity. THEN:

__ Evacuate the 5-mile radius AND 10 miles downwind as shown on Enclosure

4.2, page 2 of 4, Protective Action Zones Determination, using wind

direction

-

AND

__ Shelter remaining zones as shown on Enclosure 4.2, page 2 of 4, Protective

Action Zones Determination. using wind direction.

Enclosure 4.9

RP/O/A/5700/004

OSM Immediate and Subsequent Actions Page 3 of 4

1.2.2 Ifcontainment radiation levels DO NOT exceed the levels on Enclosure 4.2, page

2 of 4, Guidance for Determination of Gap Activity, THEN perform one of the

following:

-IF wind speed less than or equal to 5 MPH, THEN:

- Evacuate zones L, B, M, C. N, A, D, 0. R

-

AND

- Shelter zones E. F, G,I, 1. J . K, P, Q. S.

-

-

IF wind speed greater than 5 MPH, THEN:

- Evacuate the 2-mile radius I\ND 5 miles downwind as shown on Enclosure

4.2, page 3 of 4, Protective Action Zones Determination, using wind direction

-

AND

~

Shelter remaining zones as shown on Enclosure 4.2. page 3 of 4. Protective

Action 7anes Determination, using wind direction.

- 1.3 valid trip Il alarm occurs on any one of the following:

-1OR 2 EMF36(L)

1 EMF24,25,26,27

2 EMFIO, 1 I , 12, 13

THEN immediately contact RP shift at 4282 to perform HP/O/B/1009/029 (Initial Response

On-Shift Dose Assessment).

I .4 E box C (IS OCCURRING) or box D (HAS OCCURRED) from Item 10 (EMERGENCY

RELEASE) on Enclosure 4. I, (Emergency Notification Form) is checked, THEN

immediately contact RP shift at 4282 to perform HP/OIB11009/029 (Initial Response On-

Shift Dose Assessment).

Enclosure 4.9

RP/O/N5700/004

OSM Immediate and Subsequent Actions Page 4 of 4

i . 1

2. Subsequent Actions

NOTE: Site Assembly is a required on-site protective action in response to an Alert or higher

declaration. J

THEN

I

2.1 a site assembly has not already been initiated, refer to RP/O/A/5700/011

(Conducting a Site Assembly, Site Evacuation or Containment Evacuation) to evaluate and

initiate a site assembly.

-2.2 Augment shift resources to assess and respond to the emergency situation as needed.

~ 2.3 GO TO Step 3.1 in the body of this procedure and continue with the prescribed subsequent

actions.

Enclosure 4.10 RP/O/A/5700/W4

WCC SRO Immediate and Subsequent Page 1 of 2

Actions

1. Immediate Actions

Initial

NOTE: 1. Initial notification to the State and Counties must be made within 15 minutes ofthe event

declaration, using Enclosure 4.1.

2. Enclosure 4.3 has instructions for completionltransmission of the Emergency Notification

Form.

- 1. I The Emergency Coordinator shall recommend to offsite authorities in the initial notification

the following:

~~

NOTE: 1. To obtain the wind speed, use chart recorder lEEBCR9100, point #5 (Average Lower

Wind Speed).

2. To obtain the wind direction, use chart recorder lEEBCR9100, point #8 (Average

Upper Wind Direction).

3. If either point on 1EEBCR9100 is unavailable, obtain needed data from one of the

following sources in order of sequence:

A. DPC Meteorological Lab (8-594-0341)

B. National Weather Service in Greer, S.C. (864-879-1085 or

1-800-268-7785).

I - C. Catawba Nuclear Station Control Room (8-83 1-5345).

NOTE: E changes to the initial Protective Action Recommendations are recognized and approved by

the Emergency Coordinator, these shall be transmitted to the offsite agencies within 15

minutes. (PIP-M-00-01238)

1. I . I containment radiation levels exceed the levels on Enclosure 4.2. page 2 of 4,

Guidance for Determination of Gap Activity, THEN:

- 0 Evacuate the 5-mile radius AND 10 miles downwind as shown on Enclosure

4.2, page 2 of 4, Protective Action Zones Determination, using wind direction

-AND

Shelter remaining zones as shown on Enclosure 4.2. page 2 of 4, Protective

Action Zones Determination, usins wind direction.

Enclosure 4.10 RP/O/A/5700/004

-T

\ , WCC SRO Immediate and Subsequent Page 2 of 2

L.' Actions

1.1.2 Ifcontainment radiation levels DO NOT exceed the levels on Enclosure 4.2, page

2 of 4, Guidance for Determination of Gap Activity, THEN perform one of the

following:

-

IF wind speed less than or equal to 5 MPH, THEN:

__ Evacuate zones L, B, M. C,N, A, D, 0,R

-

AND

-* Shelter zones E, F, G, H, I, J, K, P, Q, S

-

-

IF wind speed greater than 5 MPH, THEN:

__ Evacuate the 2-mile radius AND 5 miles downwind as shown on Enclosure

4.2, page 3 of 4, Protective Action Zones Determination, using wind direction

.. -

AND

- Shelter remaining zones as shown on Enclosure 4.2, page 3 of 4, Protective

Action Zones Determination, using wind direction.

1.2 Complete items 1 -10, 15 and 16 on Enclosure 4.1 (Emergency Notification Form) i n

accordance with Enclosure 4.3, Section 1.

- 1.3 Make initial notification to State and County authorities using the Emergency Notification

hrm in accordance with Enclosure 4.3, Section 2.

2. Subsequent Actions

~ 2.1 Notify the NRC Operations Center by completing Enclosure 4.4 and transmitting

immediately but no later than I hour of the event declaration using RP/O/A/5700/014.

Enclosure 4.2.

2.2 Inform the OSM when this enclosure has been completed, reporting any deficiencies or

problems encountered.

I

Enclosure 4.1 1 RP/OlA/S7001004

STA Immediate and Subsequent Actions Page I of 2

1. Immediate Actions

Initial

NOTE: For a Dnll, the Community Alert Network (CAN) is not activated. I

-... NOTE: For a Drill, the Emergency Response Data System (ERDS) is not activated.

/-// ERDS can only be activated / deactivated from designated computer terminals with SDS

access. These are located in the Shift Work Managers office, the Data Coordinators

room in theTSC and all within the Control Room horseshoe area.

1.3 For an Emergency, activate the Emergency Response Data System (ERDS) as soon as

possible, but not later than one hour after the emergency declaration per the following:

f.3.1 Ensure SDS is running on the selected terminal.

1.3.2 Click on MAIN.

1.3.3 Click on GENERAL

1.3.4 Click on ERDS.

1.3.5 Click on ACTIVATE

-1.3.6 Record the time and date ERDS was activated. TIMEDATE / I

Easrern m m dd yy

1.3.7 Inform the OSM that ERDS was activated.

u -__ __ I .3.8 E ERDS failed to activate after five ( 5 ) attempts, TIfEN have an Offsite Agency

Communicator notify the NRC via ENS or other available means.

__ 1.4

Enclosure 4.1 1

STA Immediate and Subsequent Actions

RP/O/N5700/004

Page 2 of 2

For a drill, a security event exists and offsite ERO staging is desired before giving

I

instructions to report to the TSC and OSC, THEN contact Security via the ringdown phone

to the CAS/SAS, or at extension 2688 or 4900, and give instructions to activate the

TSC/OSC, according to the Emergency Response Pager Instructions for a security event

drill.

__ 1.5 For an actual emergency, a security event exists and offsite ERO staging is desired before

giving instructions to report to the TSC/OSC, THEN contact Security via the ringdown

phone to the CAS/SAS, or at extension 2688 or 4900, and give instructions to activate the

TSC/OSC, according to the Emergency Response Pager Instructions for a security event

emergency.

__ 1.6 When the security event is stabilized to the point that ERO members can come on site, go to

step 1.2.

2. Subsequent Actions

2.1 Notify one of the NRC Resident Inspectors using RP/O/A/5700/014. Enclosure 4.2.

2.2 Contact Duke Management using RP/O/A/5700/014, Enclosure 4.3 as soon as possible

.J

following event declaration.

1/ , -,.4

2.3 Inform the OSM when this enclosure has been completed, reporting any deficiencies or

problems.

NRC EXAM

2003

"-'

JPMs

-

ES-301 Control Room/In Plant Systems Outline Form ES-301-2

Facility: McGuire Date of examination:

Examination Level (circle one) : Operating Test :

1 Control Room systems (8 for RO; 7 for SRO-I; 2 0 3 for SR0-U

1I System / JPM Title

Type Codes*

Safety

Function

11 a. Respond to a Leak on RHR While in Mid-loop

(SROU)

b. Calculate Boric Acid Pot and Perform Manual

N,A,S , L

N,A,S 3

Makeup

c. Synchronize Main Generator (New Voltage N,S,A,L 4s

Regulator) (SROU)

d. Align for Cold Leg Recirculation D,A 2

e. Isolate Stuck Open PORV (Immediate Action JPM) D,A 3

(1 f . Respond to a Failure of Power Range N-42 I D,A I 7

II( g. RN Alignment after a Loss of AC Power on Unit

2 (SROU)

h. Start Up Unit 2 Lower Containment Ventilation

I1 D'C

D,C

II 8

5

Systems

~

~ ~ ~

b. Start 2A Hydrogen Analyzer

Seal Injection D

l 2

(SROU)

c.Bypass VI Dryer D,A 8

Type Codes: (Dlirect from bank, (M)odified from bank, (N)ew, (A)lternate

path, (C)ontrol room, ( S ) imulator, (L)ow-Power, (R)CA,

NUREG-1021, Draft Revision 9

OP-MC-JPM-PS-ND:206A

PAGE 1 OF 15

Prepared By:

Reviewed By:

.

Approved By:

TASK: Respond To A Leak On The ND Syst m While At Mid L OP

POSITION: RO

Operator's Name

Location: Simulator Method: Perform

Estimated JPM Completion Time : 30 Minutes

Actual JPM Completion Time: Minutes

'v'

The JPM Operator's performance was evaluated against the standards of this JPM and is

determined to be:

SATISFACTORYIUNSATISFACTORY (circle one)

Evaluator's Signature Date I I

-.

References: AP/llA/5500/19 LOSS OF ND OR ND SYSTEM LEAKAGE

JPM verified current with references by

Date I I

Rev. 00104-14-03

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-PS-ND:206A

PAGE 2 OF 15

u INITIAL CONDITIONS

Unit 1 is in mode 5 with the NC System drained to midloop

1A ND Pump in service.

The hot leg manway on 'B' S/G is removed

Cavity seals and SIG Nozzle Dams are not in service.

NCS level is at approximately 9 inches and going down.

NLO's dispatched to locate possible leak paths report that a leak exists on the suction of B

ND Pump, between 1ND-4B and the B ND Pump.

There are no draining activities in progress at this time.

Per the Control Room SRO turnover the Preferred Makeup Flow path is 1FW-27

The desired level in the NC System is 10.5 inches.

4 PT/1/N4200/002 C (Containment Closure/lntegrity) is in effect

There are no operations in progress that would reduce boron concentration.

The SRO directs you to implement AP/l/A/5500/19 (Loss of ND or ND System Leakage) and

isolate the leak.

JPM OVERALL STANDARD: B ND Train is isolated from A ND Train and NC system

cooling maintained.

NOTES:

KA 025 ,442.4 3.313.6

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-PS-ND:206A

PAGE 3 OF 15

L--,

START TIME

-

STEPS ELEMENTS STANDARD SIU COMMENT:

REQUIRED

FOR UNSAT

1 Check any ND pumps Same

running.

Cue:

Red lights lit on 1A and

1B ND pumps.

2 Check if ND pumps Same

should be stopped:

NC level -GREATER Cue:

THAN 4 INCHES

NCS level indicates 9

inches

Checks NC Subcooling Cue:

based on Core exit TIC

Greater than 0 degrees. Subcooling indicates 70

degrees

Check the following Verifies position using

valves open: OAC.

IND-1B

IND-2AC Cue:

Both valves indicate

OPEN on OAC

IF AT ANY TIME NC Operator marks "IF AT

level goes below 4 inches ANY TIME" step and

or NC Subcooling based continues in the

on core exit TICS goes procedure.

below 0 degrees,

T". ......

DENOTI S CRITICAL

OP-MC-JPM-PS-ND:206A

PAGE 4 OF 15

STEPS ELEMENTS STANDARD s/u COMMENT

REQUIRED

- FOR UNSAT

3 Check ND system flow Verifies flow less than

greater than 3000 gpm 3000 gpm. Goes to RNO

Cue:

ND flow indicates 2900

GPM.

GO TO Step 3.c. Same

Check ND pumps Verifies there are no

cavitating signs of cavitation. Goes

to RNO.

Cue:

ND s y s t e m flow a n d ND

pumps a m p s are

steady.

GO TO Step4. Same

4 Isolate containment as

follows:

4nnounce the following Wakes announcement

3n page

b Description of event

All personnel

evacuate Unit 1

containment

DENOTES CRITICAL

OP-MC-JPM-PS-ND:206A

PAGE 5 OF 15

STEPS ELEMENTS STANDARD 1 s/u COMMENl

REQUIRED

FOR UNSAT

4 CONTINUED

Actuate containment Cue:

evacuation alarm

Switch rotated.

Referto

RP/O/A/5700/011

The Control Room SRO

will refer to RP/11.

Check Determines from initial

PT/I/A/4200/002 C in conditions that PT is in

effect effect

D Notify Containment

Closure Coordinator

to initiate containment The Control 'Room SRO

closure will 'notify CCC.

5 Check if makeup

should be initiated as

follows:

=heck NC temperature - 2hecks NC temperature

3REATER THAN 200 and determines it is NOT

IEGREES F. greater than 200 degrees

=. Goes to RNO.

he:

UC temperature

ndicates 120' F.

ENOTES CRITICAL

OP-MC-JPM-PS-ND:206A

PAGE 6 OF 15

STEPS ELEMENTS STANDARD SIU COMMENT

REQUIRED

- FOR UNSAT

5 CONTINUED

Perform the following:

-IF NC level going down, Verifies NC level is still

THEN: going down.

Cue:

Level is still going

down.

Reduce or isolate Operator determines that

Letdown letdown is isolated.

Cue:

All Letdown flow paths

are isolated.

Initiates makeup as Goes to Encl.3.

required PER Encl.3 (NC

System Makeup During

Loss of ND).

6 From APll9, Enclosure Determines from initial

3 (NC System Makeup conditions that 1FW-27 is

During Loss of ND). the desired Makeup Flow

Path. Goes to End. 4.

Select Desired Makeup

Flow Path from Table 1

and initiate makeup PER

indicated enclosure.

DENOTES CRITICAL

OP-MCJPM-PS-ND:206A

PAGE 7 OF 15

STEP2 ELEMENTS STANDARD SIU COMMENT

REQUIRED

~

FOR UNSAT

7 From APll9, Enclosure

4 (Makeup By Gravity

Through IFW-27A)

Throttle 1FW-27A or

dispatch operator to

throttle as follows:

-If power available to Cue:

1FW-27A, THEN

Power is available

Place disconnect Cue:

switch for 1FW-

27A to Enable Disconnect switch in

enable

Depress 1FW-27A Cue:

open pushbutton

2-3 seconds at a 1FW-27A indicates

time. intermediate

When desired Cue:

amount of makeup

is achieved, then NC System level at

close 1FW-27A approximately 10

inches. IFW-27A closed

power lost to NIA

1 FW-27A

Nhen FWST gravity flow Operator proceeds to

ost due to one of the next step.

bllowing, then ensure

I FW-27A closed

LowFWST

inventory

NC pressure going

UP

DENOTES CRITICAL

OP-MC-JPM-PS-ND:206A

PAGE 8 OF 15

STEPS ELEMENTS STANDARD SIU COMMENT:

REQUIRED

FOR UNSAT

7 ZONTINUED

F required to maintain letermines another

SC temperature and Aakeup option is not

.vel, THEN use different ieeded

ir multiple makeup

iptions.

ieturns to body of AP-19

md goes to RNO 5.a.2.

~

8 Step 6. jame

9 tefer to

~PI0IA/57001000

10 >heck PZR level less same

han76%

he:

UCS level indicates 11

nches

DENOTES CRITICAL

OP-MC-JPM-PS-ND:206A

PAGE 9 OF 15

STEPS ELEMENTS STANDARD COMMENl

REQUIRED

FOR UNSAT

11 Isolate Letdown and

known drain paths as

follows:

Stop any NC System Determines from Initial

draining in progress conditions no draining in

progress

Close the following: Same

INV-458A Cue:

Green light lit

INV-457A Cue:

Green light lit

INV-35A Cue:

Green light lit

INV-1A he:

Sreen light lit

INV-2A he:

jreen light lit

INVJB loses 1NV-7B

he:

'ushbutton depressed,

lreen light lit

DENOTES CRITICAL

OP-MC-JPM-PS-ND:206A

-

STEP5 ELEMENTS

PAGE 10 OF 15

I STANDARD COMMENT

- REQUIRED

11 CONTINUED

Close the following ND Same

letdown valves:

INV-121 Cue:

Controller output at 0%

1 ND-32 Cue:

Green light lit

IND-17 Cue:

Pushbutton depressed,

green light lit

12 'erform the following to

omply with Tech

ipecs:

Suspend loading letermines NC system at

irradiated fuel nidloop, fuel loading

assemblies in lrould not be in progress.

- core.....

Suspend

I Determines from Initial

operations that will Conditions there are no

reduce NC boron operations in progress

concentration that will reduce boron

concentration

13 Check NC temperature

-

prior to event less Same

than 200 degrees F.

Cue:

NC temperature

indicates 120' F.

PAGE 11 OF 15

STEPS ELEMENTS STANDARD COMMENT

REQUIRED

FOR UNSAT

14 -

Check ND flow Lost Determines ND flow was

not lost. Goes to RNO

-Ifleak on ND system Determines from initial

suspected, THEN conditions that leak is on

perform one of the ND.

following:

-If makeup to NC system Determines makeup to

is maintaining NC NC system using 1FW-

inventory THEN GO TO 27A is maintaining

End. 19 (Isolation of inventory. Proceeds to

Leak on ND) End. 19 (Isolation of

Leak on ND).

-

IF loss of NC inventory NIA

imminent, THEN stop ND

pumps.

15 From AP119, Enclosure Same

19 (Isolation of Leak on

ND)

-

Check all NC pumps off he:

511 NC pumps are OFF.

16 Check NC level - letermines makeup to

STABLE OR GOING UP dC system using 1 FW-

!7A is maintaining

iventory.

he: I

ICs level indicates 11

nches and is stable

DENOTES CRITICAL

OP-MC-JPM-PS-ND:206A

PAGE 12 OF 15

-

STEPS ELEMENTS STANDARD SIU COMMENT

REQUIRED

FOR UNSAT

17 Check location of leak Given in initial conditions,

known leak is on suction of B ND

Pump.

18 Check PRT conditions Determines PRT

normal temperature, level and

pressure are normal.

Cue:

PRT temperature, level

and pressure are

normal.

19 -

IF leak is known to be Given in initial conditions.

between 1ND-I8 and The leak is between

1ND4B and IND-IgA, 1ND-46 and the B ND

THEN GO TO step 10 Pump. Operator will N/A

and continue to Step 6.

20 Check ND pump(s) -ON Same

Cue:

Red light lit for 1A ND

pump.

21 Check if leak is on Leak is on B ND train.

running ND train Operator proceeds to

suspected RNO.

22 Observe note prior to Same

Step 9 and GO TO

Step 9.

DENOTES CRITICAL

OP-MC-JPM-PS-ND:206A

PAGE 13 OF 15

STEPS ELEMENTS STANDARD SIU COMMENT:

REQUIRED

FOR UNSAT

23 Isolate train with leak, RO determines from

or both trains if affected initial conditions that train

train cannot be B ND has the leak and

determined, as follows: proceeds to isolate B

train only.

To isolate 1A ND Train: Operator determines that

A train does not need to

be isolated and proceeds

to isolate B train.

To isolate 1B ND Train: Same

Check 1B ND Pump - off Cue:

Green light lit

Close 1ND4B Cue:

Pushbutton depressed,

green light lit

Isolate 1B ND pump

discharge as follows:

close 1ND-18 Cue:

Green light lit

close IND-17 Cue:

Green light lit

close IND-15B Cue:

Pushbutton depressed,

green light lit

close 1NI-l78B Cue:

Pushbutton depressed,

green light lit

DENOTES CRITICAL

OP-MC-JPM-PS-ND:206A

PAGE 14 OF 15

-

STEPS ELEMENTS STANDARD SIU COMMENT!

REQUIRED

FOR UNSAT

23 CONTINUED

close INI-183B Cue:

Green light lit

close 1NV-840A Cue:

Green light lit

24 Determine if 1ND-1B

and IND-2AC (C NC

Loops To ND Pumps)

must be closed as

iollows:

Check the following open: Operator checked these

valves open earlier. May

check the OAC again to

verify they are still open.

1ND-1B (C NC LOOP Cue:

to ND Pumps) Both valves indicate

1ND-2AC (C NC LOOP OPEN on OAC

To ND Pumps).

Check leak - STILL Operator determines leak

EXISTS is isolated and proceeds

to RNO.

Cue:

NC system level is

stable and NLO reports

leak has stopped.

25 GO TO step 12 Same

DENOTES CRITICAL

OP-MC-JPM-PS-ND:206A

PAGE 15 OF 15

STEPS ELEMENTS STANDARD COMMENT!

REQUIRED

FOR UNSAT

26 :heck feed and bleed Operator receives cue,

ias been initiated per then proceeds to RNO.

27 5 0 TO step 14 Same

28 the following Terminate JPM with cue:

onditions met, THEN

jtop or reduce makeup cue.,. ,:,- ".'., . ' , .

low as required PER

,

... +; ..,... ',. : ;,

applicable enclosure.. ....

~; ,.

. ..

.I

.. , . .,( .

Another operator.has

been'dir$cted to

contirlu&'in this

STOP TIME

DENOTES CRITICAL

INITIAL CONDITIONS

Unit 1 is in mode 5 with the NC System drained to midloop.

1A ND Pump in service.

The hot leg manway on ' B S/G is removed

Cavity seals and S/G Nozzle Dams are not in service.

NCS level is at approximately 9 inches and going down.

NLO's dispatched to locate possible leak paths report that a leak exists on the

suction of B ND Pump, between 1ND4B and the B ND Pump.

There are no draining activities in progress at this time.

Per the Control Room SRO turnover the Preferred Makeup Flow path is 1FW-27

The desired level in the NC System is 10.5 inches.

PT/l/A/4200/002 C (Containment Closurellntegrity) is in effect

There are no operations in progress that would reduce boron concentration.

The SRO directs you to implement AP/l/A/5500/19 (Loss of ND or ND System

Leakage) and isolate the leak.

SIMULATOR OPERATORS GUIDELINES (ND:206A)

1. Reset to IC-I21

2. Freeze Simulator

3. Remove Red Tag stickers from the following:

INI-173A

INI-183B

(R04-01)

Duke Power Company (1) ID No. AP/I/N5500/019

PROCEDURE PROCESS RECORD Revision No. 015

PREPARATION

(2) Station McGuire Nuclear Station I FORMATION ONLY

N -

(3) ProcedureXtIe Loss of ND or ND System Leakage

(4) PreparedBy Hackney,Joseph S s /)tlctheM ~-

DateSeptember 4, 2002

(5) Requires NSD 228 Applicability Determination? IfApplicability Determination is required, attach NSD 228 documentatiol

Yes (New procedureor revision with major changes)

0 No (Revision with minor changes)

(QR) Date 7- //- 0 2

Cross-DisciplinaryReview By (QR) NA%Date ?-/I -02

ReactivityMgmt. Review By (QR) NA- Date 7- // -UL

Mgmt. Involvement Review By (OPS Supt.) NA- Date

(7)Additional Reviews

Reviewed By Lhhr Date q./O.DZ

Reviewed By Date

(8) TemporaryApproval (ifnecessary)

BY (OSWQR) Date

Date

Date ?-//-oz

PERFORMANCE(Compare with ControlCopy every 14 calendardays while work is kingperfomred.)

(10) Comparedwith Control Copy Date

Comparedwith Control Copy Date

(11) Date@)Performed

Work Order Number (WO#)

COMPLETION

(12) ProcedureCompletion Verification

0Yes 0 NA Check lists andlor blanksinitialed. signed, dated, or filled in NA. as appropriate?

0Yes 0 NA Requiredenclosures attached?

0Yes 0 NA Data sheets attached, completed, dated and signed?

Yes 13 NA Charts, graphs, etc. attached, dated, identified, and marked?

0 Yes 0 NA Procedure requirementsmet?

Verified By Date

(13) ProcedureCompletionApproved Date

(14) Remarks (Attachaddifionalpages, if necessary.)

-c MNS

APll/A/5500/19

UNIT 1

.--

LOSS OF N D OR N D SYSTEM LEAKAGE PAGE N O

1 Of 152

Rev. 15

A. Purpose

To identify the appropriate actions in the event of a loss of the ND System or a leak on the

ND System.

.. - --

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

APll/A15500/19 2 of 152

UNIT 1 Rev. 15

I ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

I

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

APlllA15500119 3 of 152

UNIT 1 Rev. 15

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1

C. Operator Actions

CAUTION Changes in NC pressure could result in inaccuracies in NC Level

indications.

- I. Check ND pumps -ANY RUNNING. --- GO TO Step 4.

2. Check if ND pumps should be stopped:

- a. NC Level - GREATER THAN a. Perform the following:

4 INCHES.

- 1) Stop ND pumps.

2) Close the following:

- 1ND-30A (Train A ND To Hot Leg

Isol)

- iND-33 (B

IND-18 (A ND

ND Hx

Hx Bypass)

Bypass)

- IND-15B (Train B ND To Hot Leg

-

ISOI).

- 3) Step 4

- b, Check NC subcooling based on core b. Perform the following:

exit TlCs - GREATER THAN 0" F.

- 1) Stop ND pump(s)

- 2) Ensure all NC pumps off.

3) Close the following:

- IND-30A (Train A ND To Hot Leg

Isol)

- IND-33 (A ND Hx Bypass)

- IND-18 (B ND Hx Bypass)

- IND-15B (Train B ND To Hot Leg

ISOI).

- 4) G O m S t e p 4 .

.--

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

AP/1/A15500/19 4 of 152

UNIT 1 Rev. 15

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2. (Continued)

c. Check the following valves - OPEN: c. Perform the following:

- IND-1B (C NC Loop to ND Pumps) - 1) Stop ND pump(s)

- 1ND-2AC (C NC LOOP TO ND - 2) a m s t e p 4

Pumps).

d. IF AT ANY TIME NC level goes below

4 inches NC subcooling based on

' F, THEN:

core exit TlCs goes below 0

- 1) Stop ND pump(s)

2) Close the following:

- 1ND-30A (Train A ND To Hot Leg

Isol)

- IND-33 (A ND Hx Bypass)

- IND-18 (B ND Hx Bypass)

- IND-15B (Train B ND To Hot Leg

Isol).

.

..

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

c AP/l/A/5500/19 5 of 152

UNIT 1 Rev. 15

\

I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

NOTE ND flow control valves fail open on a loss of air.

3. Check ND flow control:

- a. Check total ND System flow - - a. a m s t e p 3.c

GREATER THAN 3000 GPM.

b. Throttle as necessary to reduce ND b. Perform the following:

System to less than 3000 GPM:

- 1ND-14 (3 ND Hx Outlet)

NOTE If ND flow through

- 1ND-29 (A ND HXOutlet) any cold leg flowpath

is throttled to less

- 1ND-34 (A 8,B ND Hx Bypass). , than approximately

2000 GPM in next

step, the associated

valve will seal in and

fully close. If the

valve closes, it can

be pulsed in the open

direction to any

desired flow.

1) Throttle as necessary to reduce ND

System to less than 3000 GPM:

- INI-173A (Train A ND To A & B

CL)

- 1NI-178B (Train B ND To C & D

CL).

2) E N D pump(s) cavitating, THEN:

- a) Stop ND pump(s)

- b) ==Step4

3) Place the following manual loaders

in the full open position:

- IND-29 (A ND Hx Outlet)

- IND-14 (6ND Hx Outlet).

- 4) To Step 3.f.

- c. Check ND pump(s) - CAVITATING. - c. GOIQStep 4.

11 MNS

I LOSS OF ND OR ND SYSTEM LEAKAGE I PAGENO. 11

APll/A/5500/19

UNIT 1 I 6 of 152

Rev. 15-

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

- IND-30A (Train A ND To Hot Leg

ISOl)

- IND-15s (Train B ND To Hot Leg

Isol).

- 3) Place the manual loader for 1ND-34

(A 8, B ND Hx Bypass) in the full

open position.

.. .

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

AP/I/A/5500/19 7 Of 152

UNIT 1 Rev. 15

I ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

4. Isolate containment as follows:

a. Announce the following on page:

- 1) Description of event

- 2) "All personnel evacuate Unit 1

containment."

- b. Actuate containment evacuation alarm.

- c. REFER TO RP/O/A/5700/011

(Conducting a Site Assembly, Site

Evacuation, or Containment

Evacuation) while continuing with this

procedure.

- d. Check PT/l/A/4200/002 C - d. W m S t e p 5

(Containment Closurellntegrity) - IN

EFFECT.

- e. Notify Containment Closure Coordinator

to initiate containment closure.

~

-

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

APll /N5500/19 8 Of 152

Rev. 15

UNIT 1

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

5. Check if makeup should be initiated as

follows:

- a. Check NC temperature - GREATER a. Perform the following:

THAN 200"F.

1) NC level going down, THEN:

- Reduce or isolate letdown,

- Initiate makeup as required PER

Enclosure 3 (NC System

Makeup During Loss of ND).

- 2) m m S t e p 6.

b. Check NC parameters: b. Perform the following as required to

maintain Pzr level and subcooling:

- Pzr level - GREATER THAN 11%

(29% ACC) - 1) Maintain charging flow less than

175 GPM at all times in subsequent

- Pzr level - STABLE OR GOING UP steps.

- NC subcooling based on core exit - 2) Ensure INV-238 (Charging Line

TlCs - GREATER THAN 0" F. Flow Control) opening.

- 3) Open 1NV-241 (Seal Inj Flow

Control) while maintaining NC pump

seal flow greater than 6 GPM.

- 4) Reduce or isolate letdown

5) E subcooling or Pzr level cannot be

restored, THEN:

- a) Initiate makeup through 1NI-9A

or INI-1OB PER Enclosure 5

(Makeup Via NV Pumps

Through S/I Flow Path).

- b) IF AT ANY TIME additional flow

required to restore subcooling

and Pzr level, THEN start one NI

pump aligned to cold legs PER

Enclosure 6 (Makeup Via NI

Pumps).

- 6. REFER TO RP/O/N5700/000

(Classification of Emergency).

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

APll IA15500119 9 Of 152

UNIT 1 Rev. 15

I I I

ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

- 7. Check Pzr level - LESS THAN 76%. Perform the following:

- a. IF level has gone down in an

uncontrolled manner, NC

subcooling based on core exit TICS less

than 0" F. THEN GO TO Step 8.

- b. E level stable or going up, THEN GO

-TO Step 9.

8. Isolate letdown and known drain paths

as follows:

- a. Stop any NC System draining in

progress.

b. Close the following NV letdown isolation

valves:

- 1) INV-458A (75 GPM UD Orifice

Outlet Cont Isol).

- 2) INV-457A (45 GPM UD Orifice

Outlet Cont Isol).

- 3) INV-35A (Variable UD Orifice

Outlet Cont Isol).

- 4) INV-1A (NC UD lsol To Regen Hx).

- 5) INVQA (NC UD lsol To Regen Hx).

- 6) INV-7B (Letdown Cont Outside

Isol).

c. Close the following ND letdown valves:

- 1) INV-121 (ND Letdown Control).

- 2) IND-32 (A ND Hx To Letdown Hx).

- 3) IND-17 (B ND Hx To Letdown Hx).

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

, APll/A15500119 10of 152

UNIT 1 Rev. 15

I ACTION/EXPECTEO RESPONSE I RESPONSE NOT O B T A I N E D

- IO. Check NC temperature prior to event - Perform the following:

LESS THAN 200' F.

- a. Dump steam as required to stabilize

core exit TIC'S.

b. E leak exists inside containment & N

J

leak size is greater than capacity of

normal charging, =close the

following:

- lKC-430A (Rx Bldg Drain Hdr Cont

Outside Isol)

- IKC-429B (Rx Bldg Drain Hdr Cont

Inside Isol)

- 1WL-64A (RB Sump Pumps Disch

Cont Inside Isol)

- IWL-321A (Cont Vent Unit Drn Cont

Inside Isol)

- IWL-65B (RB Sump Pumps Disch

Cont Outside Isol)

- IWL-322B (Cont Vent Unit Drn Cont

Outside Isol).

- c. IF leak on ND suspected, THEN GO TO

Enclosure 19 (isolation of Leak On

ND).

- d. IF LOCA exists inside containment,

__-_

THEN GO TO AP/I/A15500/34

(Shutdown LOCA)

- e. a m s t e p 32.

.- -

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO

APll/A15500/19 11 of 152

UNIT 1 Rev. 15

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

- E loss of NC inventory imminent, THEN

stop ND pumps.

- 12. Check "THERMAL MARGIN' (on IMC-6) - GO TO Step 15.

GREATER THAN 30 MINUTES.

13. Check if immediate restart of ND is

available as follows:

a. Check the following: - a. -=Step 14.

- NC subcooling based on core exit

TICS - GREATER THAN 0" F

- NC level - STABLE OR GOING UP

- Suction flowpath for ND pump -

ALIGNED

- Train of ND - IMMEDIATELY

AVAILABLE TO RESTART.

- b. Check if air entrainment - KNOWN TO - b. G O m S t e p 13.d

HAVE OCCURRED.

- c. GOTlJStep 14.

- d. IF AT ANY TIME it appears that NC

subcooling based on core exit TICS may

be lost prior to restarting ND pump,

THEN GO TO Step 14.

- e. Restart ND PER Enclosure 14 (Startup - e. G O D S t e p 14

of ND Pumps).

- f. RETURN procedure and step in

effect.

MNS LOSS OF NO OR ND SYSTEM LEAKAGE PAGE NO.

APll/A/5500/19 Enclosure 3 - Page 1 of 1 46 of 152

UNIT 1 NC System Makeup During - Loss of ND Rev. 15

I I I IJ

CAUTION Use of a makeup path which contains a known NC System opening

such as Cold Leg Accumulator check valve removed or S/G primary

manwaylnoule dam removed, may reduce flow through the core.

If NC System intact and level on scale, then cold leg flow path may be

preferable for purposes of removing decay heat.

ND pumps must be off to use IND-35 (ND To FWST Isol) as a makeup

flowpath.

NOTE Makeup flow paths are not listed in any order of preference. Options used may

be dictated by NC System pressure, flow rate desired, or by availability as noted

in the Shift Supervisor checklist.

-1 Select Desired Makeup Flow Path from Table 1 and initiate makeup PER indicated

enclosure.

TABLE I

MAKEUPOW

- -__ PATHS

I'

APll/A15500/19

UNIT 1 I

LOSS OF ND OR ND SYSTEM LEAKAGE

Enclosure 4 - Page 1 of 1

Makeup By Gravity Through 1FW-27A

I

PAGE NO.

47 of 152

Rev. 15

I

NOTE Flowpath is through IFW-27A (FWST Supply To ND) back through IND-1B (C

NC Loop to ND Pumps) and IND-2AC (C NC Loop To ND Pumps).

IFW-27A (FWST Supply To ND) can be throttled in the open direction only

(seals in on closed direction).

1. Throttle IFW-27A (FWST Supply To ND) or dispatch operator to throttle as follows:

power available to 1FW-27A, THEN perform the following:

- Place power disconnect switch for 1FW-27A to enable.

- Depress 1FW-27A open pushbutton 2-3 seconds at a time.

- - WHEN desired amount of makeup is achieved, THEN close IFW-27A.

- power lost to 1PW-27A, THEN dispatch operator to throttle open 1Nv-27A (aux bldg, 695

pipechase, GG-52, 5 ft from north wall) as necessary to obtain desired level.

CAUTION With 1FW-27A (FWST Supply To ND) open, only one check valve is

available to prevent back flow from NC to FWST (if NC pressure goes

above FWST head).

2. WHEN FWST gravity flow lost due one of the following, THEN ensure IFW-27A (FWST

Supply To ND) closed:

- Low FWST inventory

- NC pressure going up.

- 3. required to maintain NC temperature or level, THEN use different or multiple makeup

options.

'

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

APll/A15500/19 Enclosure 19 - Page 1 of 14

Rev. 15

UNIT 1 Isolation of Leak On ND

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

- 1. Check all NC pumps - OFF. IF AT ANY TIME NC pump number Iseal

DIP goes below 200 PSlD OR number

seal leakoff flow goes below 0.2 GPM,

T":

- a. Stop affected NC pump@).

- b. Place Pzr spray valve in manual and

close for stopped NC pump.

- 2. Chec C level -STABLE OR GOING UP. - Initiate makeup PER Enclosure 3 (NC

System Makeup During Loss of ND)

while continuing in this enclosure.

- 3. Check location of leak - KNOWN. Try to locate leak while continuing in this

enclosure:

- Check containment floor and equipment

sump levels.

- Check NDINS sump level

- Check ND Hx room.

- Check air pressure to cavity seals and

nozzle dams.

- Check KC surge tank level.

.~ ...... . . ..~ ~ .....

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

APll/A/5500/19 Enclosure 19 - Page 2 of 14 140 of 152

Rev. 15

UNIT 1 Isolation of Leak On ND

ACT I ON/ EXPECTED RESPONSE I RESPONSE NOT OBTAINED

- 4. Check PRT conditions - NORMAL. IF open

- relief valve suspected, THEN

perform the following:

- a. Evaluate lowering NC pressure to

reseat valve.

b. E desired to lower NC pressure, THEN:

- Trip NC pump(s) prior to reducing

number 1 seal DIP less than

200 PSID.

- Reduce NC pressure.

- Initiate cooldown of NC system as

necessary to maintain NC subcooling

greater than 0" F.

- c. IF AT ANY TIME containment pressure

reaches 1 PSIG, THEN observe notes

prior to Step 9 and CO To Step 9 to

isolate leak.

d. Dispatch operator to check the following

valves For input to the PRT:

- containment conditions allow,

THEN dispatch operator to check

IND-3 (NC Loop 3 Discharge to ND

System Safety Relief) (Unit 1 reactor

bldg, 738+3, 184 degrees, B and C

Fan room)

- 8 1ND-56 (A ND HX Outlet to Nl

System Cold Leg Relief) (aux bldg,

733+9, GG-52. midget hole)

- IND-61 (ND HX Outlet To NI System

Hot Leg Injection Safety Relief) (aux

bldg, 733+11, JJ-52, rathole)

- 1ND-64 (B ND HX Outlet To NI

System Cold Leg Injection Safety

Relief) (aux bldg, 733+6, "-52,

room 730, mechanical penetration

room).

-e. leak stopped, THEN GO TO Step 12.

- 5. E leak known to be between 1ND-1B (C

NC Loop to ND Pumps) and ND pump

suction valves (1ND-19A and 1ND-4B),

THEN GO TO Step 10.

I I

I I i

I

I ACTION/EXPECTED RESPONSE RESPONSE NOT O B T A I N E D

- 6. Check ND pump@) -ON. - Observe notes prior to Step 9 and !

Step 9.

- 7. Check if leak on running ND train - - Observe notes prior to Step 9 and

SUSPECTED. Step 9.

8. Swap operating trains of ND as follows:

- a. IF both ND pumps running in RHR,

THEN observe notes prior to Step 9 and

_

GO _ TO Step 9.

b. Obtain the following procedures while

continuing with Step 8.c:

- OP/l/A/610O/S0-6 (Placing The

Second ND Train In Service)

- OP/l/A/6100/SU-14 (Removing ND

From Service)

- OP/l/A/61OO/SO-7(Swapping ND

Injection Paths).

- c. IF AT ANY TIME it is necessary to

secure running ND pump(s) prior to

completing train swap, THEN observe

notes prior to Step 9 and Step 9

d. On running ND pumps, check normal - d. Realign discharge flowpath to normal

discharge flowpath - ALIGNED: PER OP/l/A/610O/SO-7 (Swapping ND

Injection Paths).

- 1A ND pump: 1NI-173A (Train A ND

TO A & B CL) - OPEN.

- 1B ND pump: INI-178B (Train B ND

To C & D CL) -OPEN.

e. Establish KC flow to ND Hx to be

placed in service as follows:

- To establish KC flow to 1A ND Hx,

GO _

_ TO Step 8.f.

- To establish KC flow to 1B ND Hx,

Step 8.g.

'1

,

v

AP/I/A15500/19

UNIT 1

LOSS OF 'ND OR ND SYSTEM LEAKAGE

Enclosure 19 - Page 4 -',.

Isolation of Leak OnI ND

A

1 PAGENO.

142 of 152

Rev. 15

1

1' I -

I I I 1

ACTION/EXPECTEO RESPONSE I RESPONSE NOT OBTAINED

8. (Continued)

f. Establish KC flow to 1A ND Hx as

follows:

- 1) Check 1A RN pump -AVAILABLE. - I) Step 8.f.4).

- 2) Start 1A RN pump.

3) Start 1A KC pumps as follows:

- a) Select "AUTO on 1KC-51A

(Train A Recirc Isol).

- b) Start 1 A l and 1A2 KC pumps.

- 4) Ensure RN flow established to KC

Hx in operation.

5) IF AT ANY TIME adequate KC flow

to 1A ND Hx cannot be established,

THEN throttle closed the following

valves as required:

- IKC-149 (A KF Hx Outlet Flow)

- . IKC-156 (B KF Hx Outlet Flow).

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

,- AP/I/A/5500/19 Enclosure 19 - Page 5 of 14 143 of 152

Rev. 15

L - UNIT 1 Isolation of Leak On ND

I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. (Continued)

- 6) Throttle open 1KC-56A (KC To A 6) Evaluate opening KC cross-tie

ND Hx) to establish 2000 GPM to valves to establish flow from other

5000 GPM KC flow to 1A ND Hx, train as follows:

while limiting each KC pump flow to

4000 GPM. a) Open:

- 1KC-1A (Trn A Aux Bldg Non

Ess Ret Isol)

- IKC-2B (Trn B Aux Bldg Non

Ess Ret Isol).

b) Open:

- 1KC-50A (Tm A AuX Bldg

Non Ess Sup Isol)

- 1KC-53B ( l m B Aux Bldg

Non Ess Sup Isol).

- 7) Observe note prior to Step 8.h and

_

GO _TO Step 8.h.

..

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO

AP/I/A/5500/19 Enclosure 19 - Page 6 of 14 144 of 152

Rev 15

UNIT 1 Isolation of Leak On ND

ACTION/EXPECTED RESPONSE I 1 RESPONSE NOT OBTAINED

8. (Continued)

g. Establish KC flow to 1B ND Hx as

follows:

- 1) Check 1B RN Pump - AVAILABLE. - 1) aTo Step 8.9.4).

- 2) Start 1B RN Pump.

3) Start KC pumps as follows:

- a) Select "AUTO on 1KC-54B

(Train B Recirc Isol).

- b) Stair 1B1 and 1B2 KC Pumps.

- 4) Ensure RN flow established to KC

Hx in operation.

5) IF AT ANY TIME adequate KC flow

to 1B ND Hx cannot be established,

THEN throttle closed the following

valves as required:

- IKC-149 (A KF Hx Outlet Flow)

- IKC-156 (6KF Hx Outlet Flow).

.--

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

AP/I/A/5500/19 Enclosure 19 - Page 7 of 14 145 of 15:

II 1

C,,U"JI

UNIT 1 Isolation of Leak On ND

lsolat Rev. 15

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

NOTE If NC temperature is greater than 200' F, OP/l/A/61OO/SU-14 (Removing

ND From Service) requires cooling down ND discharge header to 180 F

prior to securing pump. This requirement may be waived if isolating leak is

time critical.

- Reading Limits and Precautions section of the following OPs may be

waived if isolating leak is time critical.

- h. Start opposite train ND PER

OP/1/A/6100/SO-6 (Placing The

Second ND Train In Service).

- i. Shutdown train with leak PER

OP/l/A/610O/SU-14 (Removing ND

From Service).

- j. Do not continue until train swap

complete

LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

APII /A15500119 146 of 152

Enclosure 19 - Page 8 of 14

UNIT 1 Isolation of Leak On ND Rev 15

ACTION/EXPECTEO RESPONSE RESPONSE NOT OBTAINED

NOTE If location of leak unknown, isolating trains one at a time may identify which

train is leaking.

If ND pump running and location of leak unknown, isolating idle train first may

avoid loss of ND.

9. Isolate train with leak, or both trains if

affected train cannot be determined, as

follows:

To isolate 1A ND Train:

- a. Check 1A ND Pump - OFF. a. Perform the following:

- 1) Stop 1A ND pump.

2) both ND pumps off, THEN:

- a) Have another licensed

operator continue with this

enclosure.

- b) RETURN To Step 12 in body

of this procedure.

--b. Close IND-19A (A ND Pump Suct b. E IND-19A still open, THEN

From FWST or NC). evaluate performing the following:

- 1) Stop 1B ND Pump

2) Dispatch operator to close the

following breakers:

- 1EMXD - 08D (C NC LOOPTO

ND Pumps 1ND-1B), (1 . ETB

Room)

- 1EMXA4 - 03C (C NC LOOPTO

ND Pumps 1ND-2A) (IETA

Room)

(RNO continued on next page)

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

147 of 152

APll/A/5500/19 Enclosure 19 - Page 9 of 14

Rev. 15

UNIT 1 Isolation of Leak On ND

ACTIONlEXPECTEO RESPONSE RESPONSE NOT OBTAINED

9. (Continued)

3) Close the following valves:

- IND-1B (C NC Loop to ND

Pumps)

- 1ND-2AC (C NC LOOP'TOND

Pumps).

- 4) Close IND-19A,

c. Isolate 1A ND pump discharge as c. Dispatch operator to close affected

follows: valve(s):

- Close 1ND-33 (A ND Hx Bypass) - IND-33 (aux bldg, 733+8, LL-52,

room 732, ND heat exchanger

- Close IND-32 (A ND Hx To room 1B)

Letdown Hx)

- IND-32 (aux bldg, 733+6, 1A ND

- Close 1ND-30A (Train A ND To Hx Room, 3 feet from west wall

Hot Leg lsol) and 1 foot from south wall)

- Close INI-173A (Train A ND To A - IND-30A (aux bldg, 733+4, LL-52,

& 8 CL) room 733, ND heat exchanger

room I A , 1 ft from east, 8 ft from

- Close 1NI-1838 (ND To B 8, C Hot south)

Legs Isol)

- INI-173A (aux bldg, 716+21.

-~- Close 1NV-840A (ND To Pzr Aux GG-52, room 602, midget hole

Spray Control). near reactor bldg wall above ledge,

4 ft south of GG-52 near VCT

area)

- 1NI-183B (aux bldg, 733+10,

FF-52, room 602, midget hole,

enter from electrical penetration

room, 4 ft from reactor bldg wall, 3

ft from ceiling)

- INV-840A (aux bldg, 733+8.

KK-53, room 732, west of NS heat

exchanger room IB).

.

I II MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

I

AP/I/A/5500/19

UNIT 1 S

I

Enclosure 19 - Page 10 of 14

Isolation of Leak On ND

I I

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

9. (Continued)

To isolate 18 ND Train:

- a. Check 1B ND Pump - OFF. a. Perform the following:

- 1) Stop I B ND pump.

2) E both ND pumps off, THEN:

- a) Have another licensed

operator continue with this

enclosure.

- b) RETURN To Step 12 in body

of this procedure.

- b. Close IND-4B (B ND Pump Suct b. 1ND4B still open, THEN evaluate

From FWST or NC). performing the following:

- 1) Stop 1A ND Pump.

2) Dispatch operator to close the

following breakers:

- IEMXD-08D (C NC LOOPTO

ND Pumps IND-1B) (IETBI~

Room)

- 1EMXA4-03C (C NC LOOP TO

ND Pumps IND-2A) (IETA

Room)

3) Close the following valves:

- 1ND-1B (C NC LOOP to ND

Pumps)

- 1ND-2AC (C NC Loop To ND

Pumps).

- 4) Close IND-4B.

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

AP/I/A/5500/19 149 of 152

Enclosure 19 - Page 11 of 14

UNIT 1 Isolation of Leak On ND Rev. 15

I

I I

I

ACTION/EXPECTEO RESPONSE RESPONSE NOT OBTAINED

9. (Continued)

c. Isolate 1B ND pump discharge as c. Dispatch operator to close affected

follows: valve(s):

- Close IND-18 (B ND Hx Bypass) - IND-18 (aux bldg, 733+8, LL-52,

room 732, ND heat exchanger

- Close IND-17 (B ND Hx To room 16)

Letdown Hx)

- IND-17 (aux bldg, 733+12, 1B ND

- Close IND-156 (Train B ND To Hx Room, 3 feet from west wall

Hot Leg Isol) and 10 feet from south wall)

- Close INI-1788 (Train B ND To C - IND-158 (aux bldg, 733+8, LL-51,

& D CL) room 732, ND Hx room 16)

- Close INI-1838 (ND To B & C Hot - 1NI-1788 (aux bldg, 733+6,

Legs Isol) -52, room 730, BIT room 6 ft

west of -52, 3 ft from reactor

- Close 1NV-840A (ND To Pzr Aux bldg wall)

Spray Control).

- 1Ni-1838 (aux bldg, 733+10,

FF-52, room 602, midget hole,

enter from electrical penetration

room, 4 ft from reactor bldg wall, 3

ft from ceiling)

- 1NV-840A (aux bldg, 733+8,

KK-53, room 732, west of NS heat

exchanger room 16).

10. Determine if IND-1B and IND-2AC (C NC

Loop To ND Pumps) must be closed as

follows:

a. Check the following open: - a. GOTO Step 11

- 1ND-I B (C NC Loop to ND Pumps)

- IND-2AC (C NC Loop To ND

Pumps).

- b. Check leak - STILL EXISTS. - b. G O m S t e p 12,

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

APlllAl5500l19 150 of 152

Enclosure 19 - Page 12 of 14

UNIT 1 Isolation of Leak On ND Rev. 15

ACT I ON / EXPECTED RESPONSE RESPONSE NOT OBTAINED

I

IO. (Continued)

- c. Check NC temperature prior to event - - c. IF AT ANY TIME containment pressure

LESS THAN 200" F. reaches 1 PSlG AND leak still exists,

__-_

THEN GO TO Step 10.f to immediately

isolate ND leak,

NOTE If core cooling can be maintained, it may be desirable to delay closing

IND-16 and IND-2AC while trying alternative methods to isolate leak.

- d. Evaluate closing 1ND-1B and 1ND-2AC

based on leak size and location.

- e. Check closure of 1ND-16 and IND-2AC - e. GOTCJStep 11.

- REQUIRED.

f. Close the following breakers:

- IEMXD - 08D (C NC Loop To ND

Pumps IND-1B) (IETB Room)

- 1EMXA4 - 03C (C NC Loop TO ND

Pumps IND-2A) (IETA Room).

- g. Stop all ND pumps

h. Close the following valves:

I

IND-16

- IND-2AC.

i. Check the following valves - CLOSED. - i. Evaluate closing valves to complete

leak isolation.

- IND-19A (A ND Pump Suct From

FWST or NC)

- IND-46 (6 ND Pump Suct From

FWST or NC).

.--

MNS LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

AP/l/A/5500/19 Enclosure 19 - Page 13 of 14 151 of 152

Rev. 15

UNIT 1 Isolation of Leak On ND

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

- 11. Check leak - ISOLATED. Perform the following:

- a. REFER TO AP/I/A/5500/10 (NC

System Leakage Within The

Capacity Of Both NV Pumps), for

additional guidance in locating the leak.

- b. E refueling canal level going down,

THEN REFER TO AP/l/A/5500/40

(Loss Of Refueling Cavity Level).

- 12. Check Feed and Bleed -HAS BEEN - GO TO Step 14.

INITIATED PER STEP 19 IN BODY OF

THIS PROCEDURE.

- 13. _ GO - TO Step 15.

14. WHEN the following conditions met,

i "stop or reduce makeup flow as

required PER applicable enclosure:

- NC subcooling based on core exit T/Cs -

GREATER THAN 0' F

NC level is greater than one of the

following:

.~

- Pzr level on scale prior to event,

THEN check Pzr level - GREATER

THAN 11%

- E NC System drained prior to event,

THEN check NC level - GREATER

THAN 10 INCHES.

I II MNS

AP/I/A/5500/19

LOSS OF ND OR ND SYSTEM LEAKAGE PAGE NO.

Enclosure 19 - Page 14 of 14 152 of 152

UNIT 1 Isolation of Leak On ND Rev. 15

ACTION/EXPECTEO RESPONSE RESPONSE NOT O B T A I N E D

15. tube leak on letdown HX identified,

T":

- a. Ensure letdown flowpaths have been

isolated.

- b. Close INV-124 (Letdown Pressure

Control).

- c. Place INV-137A (NC Filters 0th 3-Way

Cntrl) to "HUT".

- 16. tube leak on ND HX identified, THEN

evaluate isolating KC to affected HX.

- 17. Check ND pump - RUNNING. - RETURN To step in effect in body of this

procedure.

- 18. Check leak - STOPPED. Perform the following:

- a. Continue efforts to isolate leak

- b. Continue monitoring makeup source

levels (FWST, VCT).

- c. IF AT ANY TIME ND train needs to be

isolated to stop leak, THEN RETURN

m S t e p 1.

- d. Do not continue until leak isolated.

- 19. Notify station management to arrange for

inspection of temporary thimble seals or

other equipment that may have been

affected by this event.

- 20. RETURN procedure and step in

effect.

OP-MC-JPM-PS-NV:207A

PAGE 1 OF 8

Prepared By:

Reviewed By:

Approved By:

TASK: Calculate Boric Acid Potentiometer Setting and begin Manual

Makeup to VCT

POSITION: RO

Operator's Name

Location: Simulator Method: Perform

Estimated JPM Completion Time: 20 Minutes

-/ Actual JPM Completion Time: Minutes

The JPM Operator's performance was evaluated against the standards of this JPM and

is determined to be:

SATISFACTORYIUNSATISFACTORY (circle one)

Evaluator's-Signature Date I I

References: 0Pll1A/6150/009 Boron Concentration Control

0P/1/A/6100122 Unit 1 Data Book

JPM verified current with references by

Date I I

Rev. 00104-16-03

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-PS-NV207A

PAGE 2 OF 8

i/

INITIAL CONDITIONS

IAE testing has the automatic portion of the NC SYS M/U Controller out of

service.

NC SYS M/U Controller is in the OFF position

VCT level 42%-

BAT Boron Concentration 7000 ppm

NC System Boron Concentration 950 ppm

Blender Flow Rate 90 gpm

All Initial Conditions have been satisfied for OP/l/A/6150/009 Encl. 4.5 (Manua

Makeup to VCT using NC System Makeup Controller).

NV System is in normal operation per OP/l/A/6200/001A

There are no outstanding R&Rs that will impact the performance of

OP/l/A/6150/009 Encl. 4.5 (Manual Makeup to VCT using NC System MakeuF

Controller).

The Control Room SRO directs you raise VCT level to 54% using OPll/A16150/009

Encl. 4.5 (Manual Makeup to VCT using NC System Makeup Controller).

JPM OVERALL STANDARD: A set point of approximately 3.1 is calculated for the

BA Flow Control potentiometer. Manual make up is

terminated when actual Boric acid flow is observed to

be greater than calculated.

NOTES: When makeup is started, a malfunction that causes

Boric Acid flow to increase from 12 to 20 GPM will be

ramped in over 30 seconds.

KA 004 A4.02 3.8/3.9

W

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-PS-NV207A

PAGE 3 OF 8

u

START TIME

STEPS ELEMENTS STANDARD SIU COMMENl

REQUIRED

FOR UNSAT

1 two boric acid pumps Determines NC

required to achieve system Boron

desired NC system concentration is less

boron concentration, than 2200ppm and will

go to Encl. 4.15 not need both pumps

Evaluate all Determines from initial

outstanding R&Rs that conditions that R&Rs

may impact the have already been

performance of this evaluated

procedure

Check NV System is in Determines from initial

normal operation per conditions that NV

OP/1/A/6200/001 A system is aligned

(Chemical and Volume normally.

Control System

Letdown)

4 When changing NC Determine from initial

system boron conditions NC system

concentration, evaluate boron concentration

energizing additional will not be changed

PZR heaters to

enhance mixing.

5 Set Total Make Up Same

Flow Counter to

desired value

DENOTES CRITICAL

OP-MC-JPM-PS-NV207A

PAGE 4 OF 8

STEPS ELEMENTS STANDARD s/u COMMEN'T

REQUIRED

FOR UNSAT

6 When Total Make Up Value does not

Flow Counter cover change when cover

closed, check counter closed

at desired value

7 Set Boric Acid Flow I Same

8 When Boric Acid Flow Value does not

Counter cover closed, change when cover

check counter at closed

desired value

9 Determine BA ~l~~

16

BA FIOW

Control" potentiometer

setpoint for desired

Boron Concentration

using the McGuire Book Table 5.2 as

Data Book or OAC follows:

950 PPM x 90 GPM

7000 PPM

12.2 GPM Acid = 3.05

4

Potentiometer

-

Setting of 2.95 3.15

is acceDtable.

DENOTES CRITICAL

OP-MC-JPM-PS-NV:207A

PAGE 5 OF 8

STEPS ELEMENTS STANDARD COMMENT

REQUIRED

FOR UNSAT

I0 jet BA Flow Control 3A Flow Control

iotentiometer iotentiometer set at

approx. 3.1

-

2.95 3.15 is

acceptable)

Cue:

Potentiometer set as

calculated.

I1 Select "MANUAL" on Same

"NC SYS M/U

Controller" Cue:

Switch placed in

Manual

I2 Open 1NV-175A (BA Same

Blender to VCT Outlet)

Cue:

Switch rotated to

Open

Ensure in Auto Same

13

BA Blend Disch Cue:

CNTRL

Controllers in Auto

BA Flow Control

DENOTES CRITICAL

OP-MC-JPM-PS-NV207A

PAGE 6 OF 8

STEPS ELEMENTS STANDARD SIU COMMENT

REQUIRED

FOR UNSAT

14 -If both BA Trans same

Pumps off, Ensure in

AUTO

IABATrans Zue:

Pump

or I B BA Trans pump is

n the start position

1B BATrans

and on for recirc

Pump

Ensure in AUTO one of Same

15

the following:

IARXMN Cue:

Water Pump

One of the RX MIU

or Water Pumps is in

1B RXMIU AUTO

Water Pump

Momentarily select Same

I6

START on "NC System

Make Up" Cue:

Switch rotated to

START

Check lit NC System Same

17

Make Up red light

Cue:

Red light is lit

Ensure throttled Same

18

INV-252A Cue:

INV-267A

Valves indicate

intermediate position

DENOTES CRITICAL

OP-MC-JPMPS-NV:207A

PAGE 7 OF 8

~

STEPS ELEMENTS STANDARD SIU COMMENl

REQUIRED

FOR UNSAT

19 Ensure RX MIU Water Same

Pump starts

Cue:

RX MIU Water Pump

selected to AUTO

starts

20 in AUTO, Ensure BA Operator will NIA step

rrans Pump starts and continue.

Cue:

1B BA Trans pump is

in the start position

and on for recirc

21 Znsure acceptable Operator checks chart

3eactor Makeup Water recorder to verify

m d Boric Acid flow. adequate flow. (Boric

acid flow should be

approx. 12.2 GPM,

Total blend flow = 90

GPM.)

Cue:

Boric Acid flow is

approx. 20 gpm.

22 'er note in procedure, Same

iperator terminates

nakeup to VCT by Cue:

)lacing NC Make Up

zontrol to STOP. Switch rotated to

STOP

DENOTES CRITICAL

OP-MC-JPM-PS-NV207A

PAGE 8 OF 8

- ~

STEPS ELEMENTS STANDARD SIU COMMENl

REQUIRED

FOR UNSAT

iform SRO that make Terminate JPM with:

23

p was terminated.

The Control Room

SRO will investigate

problem and have

another RO complete

makeup.

STOP TIME

DENOTES CRITICAL

INITIAL CONDITIONS

IAE testing has the automatic portion of the NC SYS M/U Controller out of

service.

NC SYS M/U Controller is in the OFF position

VCTlevel 42%

BAT Boron Concentration 7000 ppm

NC System Boron Concentration 950 ppm

Blender Flow Rate 90 gpm

All Initial Conditions have been satisfied for OP/1/A/6150/009 Encl. 4.5 (Manual

Makeup to VCT using NC System Makeup Controller).

NV System is in normal operation per OP/1/A/6200/001A

There are no outstanding R&Rs that will impact the performance of

OP/1/A/6150/009 Encl. 4.5 (Manual Makeup to VCT using NC System Makeup

Controller).

The Control Room SRO directs you raise VCT level to 54% using OP/1/A/6150/009

End. 4.5 (Manual Makeup to VCT using NC System Makeup Controller).

.

SIMULATOR OPERATIONAL GUIDELINES (NV-207A)

1. Reset the Simulator to IC-122

2. Insert: OVR NV088B, Set = 50, Ramp = 30

3. Freeze the simulator

4. Insert malfunction when make up is started.

(R04-01)

Duke Power Company il) ID NO. OP/l/N6150/009

PROCEDURE PROCESS RECORD Revislon No. 066

?E PARATION

2) Station McGuire Nuclear Station

I~FORM~TIO 0~~ ~ 1 ~

\,-

(3) Procedure Title Boron Concentration Control

(4) Prepared By Penson,Rhonda A Date March 3,2003

I

(5) Requires NSD 228 Applicability Determination? If Applicability Determination is required, attach NSD 228 documentation.

Yes (New procedure or revision with major changes)

(QR)

(QR) NA %Date Date* ^Y

. (QR) NA-

Mgmt. Involvement Review By (OPS Supt.) NA&& Date

Date*

(7) Additional Reviews

Reviewed By Date

(8) TemporaryApproval (if necessary)

BY (OSM/QR) Date

BY n (OR) Date

\,(9) Approved By Date 3/9/23

PERFORMANCE (Compare with Control Copy every 14 calendar days while work is beingperfonned.)

(10) Compared with Control Copy Date

Compared with Control Copy Date

Compared with Control Copy Date _.

(11) Date@)Performed

Work Order Number P O # )

COMPLETION

(1 2) Procedure Completion Verification

0 Yes [I] NA Check lists and/or blanks initialed, signed, dated, or filled in NA. as appropriate?

0 Yes 0 NA Required enclosures attached?

Yes [I] NA Data sheets attached, completed, dated and signed?

0 Yes NA Charts, graphs, etc. attached, dated, identified, and marked?

Yes 0 NA Procedure requirements met?

Verified By Date

(1 3) Procedure Completion Approved Date

(14) Remarks (Attach additional pages, if necessary.)

Fom based on NSD 703 App D (Procedure Ircccss Record)

Enclosure 4.5 OP/1/A/6 I50/009

Manual Makeup to VCT Using "NC System Page 1 of 6

Makeup" Controller

'W'

1. Limits and Precautions

1.I WHEN changing NC System boron concentration, a minimum of one NC Pump shall be

in operation to ensure adequate mixing of NC loops, with the following exceptions:

(SOER 94-2) (PIP-M99-2915)

Boration per Abnormal or Emergency Procedures

Both the NC System and makeup source greater than required boron concentration

(Shutdown Margin, refueling concentration)

1.2 WHEN reactor subcritical and count rate on either Source Range Channel increases by a

factor of two or more during a Boron Concentration change, the operation must be

immediately stopped until a satisfactory evaluation of the situation has been made.

1.3 Dilution operations are limited by available capacity in RHT.

1.4 Piping downstream of Blender will contain 20 - 35 gallons of fluid at previous makeup

concentration.

1.5 Dual Boric Acid Tank Pump operation is minimized due to potential to deadhead weaker

Pump.

'~V During dilution of NC System with Shutdown Banks A and B withdrawn, at least two

1.6

NC Pumps shall be operating, one of which in NC Loop to which charging is aligned.

(PP-M02-3372)

2. Initial Conditions

None

3. Procedure

NOTE: Operation of two Boric Acid pumps may be required with high NC System boron

concentration.

0 3.1 two boric acid pumps required to achieve desired NC System boron concentration, go

to Enclosure 4.15 (VCT Makeup With High NC System Boron Concentration),

0 3.2 Evaluate all outstanding R&Rs that may impact performance of this procedure.

W Unit 1

Enclosure 4.5 01'/1/A/6 150/009

Manual Makeup to VCT Using "NC System Page 2 of 6

Makeup" Controller

L/

CAUTION: NSD 304 (Reactivity Management), states that Operations shall be responsible for

control of reactivity and taking conservative actions to safeguard integrity of reactor

fuel.

NOTE: Comparison of Total Make Up Flow Counter to Boric Acid Flow Counter ratio can be

used as alternate indication of boron concentration in makeup.

0 3.3 Check NV System in normal operation per OP/l/A/6200/001 A (Chemical and Volume

Control System Letdown).

0 3.4 WHEN changing NC System boron concentration, evaluate energizing additional

pressurizer heaters to enhance system mixing.

CAUTION: Total Makeup and Boric Acid Flow integrator thumbwheels are set too low, boric

acid flow or reactor makeup water flow may be automatically terminated, resulting in

inadvertent dilution or boration of NC System.

.

NOTE: Integrator Thumbwheel covers should NOT be opened unless associated counter reset

'\/' pushbutton depressed.

Excessive operation of Integrator Thumbwheel covers should be avoided.

Integrator Thumbwheel covers must be closed for NC Makeup System to operate.

0 3.5 Set Total Make Up Flow Counter to desired value.

0 3.6 WHEN Total Make Up Flow Counter cover closed, check counter at desired value.

0 3.7 Set Boric Acid Flow Counter to desired value.

0 3.8 WHEN Boric Acid Flow Counter cover closed, check counter at desired value.

0 3.9 Determine "BA Flow Control" potentiometer setpoint for desired Boron Concentration

using McGuire Data Book or OAC.

0 3.10 Set "BA Flow Control" potentiometer.

0 3.11 Select "MANUAL" on "NC SYS M/U Controller".

0 3.12 Open lNV-l75A (BA Blender To VCT Outlet).

Unit 1

Enclosure 4.5 OP/1/A/6 150/009

Manual Makeup to VCT Using "NC System Page 3 of 6

Makeup" Controller

'U'

3.13 Ensure in "AUTO":

Ci "BA Blend Disch CNTRL"

0 "BA Flow Control"

0 3.14 E both BA Trans Pumps off, ensure in "AUTO" one of the following:

0 1A BA Trans Pump

0 F B A Trans Pump

3.15 Ensure in "AUTO" one of the following:

1A Rx M N Water Pump

1B~x M/U Water Pump

NOTE: The following step initiates blended flow to VCT.

"NC Make Up Control" can be placed in "STOP" to terminate makeup at anytime.

Steps 3.16 - 3.25 may be completed AND then checked off as time allows.

0 3.16 Momentarily select "START" on "NC System Make Up"

0 3.17 Check lit "NC System Make Up" red light.

3.18 Ensure throttled:

0 1NV-252A (RX M/U Water To Blender Control)

0 1NV-267A (Boric Acid To Blender Control)

0 3.19 Ensure Rx M/U Water Pump starts

0 3.20 E in "AUTO", ensure BA Trans Pump starts.

3.21 Ensure acceptable:

0 Reactor makeup water flow

0 Boric acid flow

Unit 1

Enclosure 4.5 OP/1/A/6150/009

Manual Makeup to VCT Using "NC System Page 4 of 6

Makeup" Controller

u 0 3.22 Monitor the following parameters:

SM Pressure

Reactor Power

Tavg

Rodmotion

0 3.23 plant parameters indicate other than expected response, perform the following:

0 Select "STOP" on "NC System Make Up"

0 Check lit "NC System Make Up" green light

0 Notify CR SRO

0 3.24 "NC System Make Up" placed in "STOP" to terminate makeup AND it is desired to

re-initiate makeup, go to Step 3.5.

0 3.25 WHEN VCT at desired level, select "STOP on "NC System Make Up",

0 3.26 Check lit "NC System Make Up" green light.

0 3.27 in "AUTO", ensure off

0 1A BA Trans Pump

L'

0 1B BA Trans Pump

0 1A Rx M/u Water Pump

0 1B Rx M/U Water Pump

3.28 Ensure closed:

0 1NV-252A (RXM/U Water To Blender Control)

0 1NV-267A (Boric Acid To Blender Control)

17 3.29 -Ensure in "AUTO" 1NV-175A (BA Blender To VCT Outlet).

Unit 1

Enclosure 4.5

Manual Makeup to VCT Using "NC System Page 5 of 6

Makeup" Controller

i/

NOTE: CR SRO concurrence required if flush of blender NOT performed.

0 3.30 E desired to flush blender, perform the following:

0 Go to Enclosure 4.4 (Alternate Dilute) and flush with 20 - 35 gallons reactor makeup

water through 1NV-175A (BA Blender to VCT Outlet).

-

0 Go to Enclosure 4.2 (Borate) and flush with 20 - 35 gallons boric acid through

1NV-175A (BA Blender to VCT Outlet).

0 3.3 1 Record in Auto Log final blender contents:

0 Rw Makeup Water

0 6 i c Acid

0 3.32 automatic makeup alignment desired, perform the following:

i i 0 3.32.1 Determine "BA Flow Control" potentiometer setpoint for desired boron

concentration using McGuire Data Book or OAC.

0 3.32.2 Set "BA Flow Control" potentiometer

0 3.32.3 Ensure set for 90 gpm (= 5.6) "BA Blend Disch Cntrl" potentiometer.

3.32.4 Ensure in "AUTO":

- 0 1NV-171A (BA Blender to VCT Inlet)

0 1NV-175A (BA Blender To VCT Outlet)

0 1NV-267A (Boric Acid To Blender Control)

0 1"-252A (RX MIU Water To Blender Control)

0 "BA Blend Disch Cntrl" MadAuto Station

0 "BA Flow Control" MadAuto Station

0 "NC Sys M/U Controller"

Unit 1

Enclosure 4.5 OPIkAI6 150/009

Manual Makeup to VCT Using "NC System Page 6 of 6

Makeup" Controller

c- 3.32.5 Select "AUTO" on one of the following:

0 1A Rx M/U Water Pump

~BRX MU Water Pump

0 3.32.6 both BA Trans Pumps off, select "AUTO" on one of the following:

0 1A BA Trans Pump

0 K B A Trans Pump

NOTE: The following step anns auto makeup.

0 3.32.7 Momentarily select "START' on "NC System Make Up".

0 3.32.8 Check lit "NC System Make Up" red light.

3.32.9 Ensure the following reset to zero:

0 Total Make Up Flow Counter

0 Boric Acid How Counter

End of Enclosure

ii Unit 1

OP-MC-JPM-GEN-MG:205A

PAGE 1 OF 11

Prepared By:

L-' Reviewed By:

Approved By:

TASK: Place Main Generator Voltage Regulator in service and Synchronize to Grid

POSITION: RO

Operator's Name

Location: Simulator Method: Perform

Estimated JPM Completion Time: 30 Minutes

Actual JPM Completion Time: __ Minutes

w The JPM Operator's performance was evaluated against the standards of this JPM and is

determined to be:

SATISFACTORYIUNSATISFACTORY (circle one)

Evaluator's Signature Date I I

References: OPll/A/63OOlOO1 Turbine Generator Startup/Shutdown

JPM verified current with references by

Date I I

Rev. 00104-14-03

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-GEN-MG:205A

PAGE 2 OF 11

L

INITIAL CONDITIONS

You are the Unit 1 Balance of Plant (BOP).

Unit 1 is being maintained between 12% and 15% RTP per OP/1/A/61001003 (Controlling

Procedure for Unit Operation) End. 4.1 (Power Increase) by another Reactor Operator.

All Initial Conditions and steps in OPll/A/6300/001 (Turbine Generator Startup/Shutdown)

Encl. 4.1 (Automatic Mode Startup) have been completed up through step 3.10.

System Engineer has requested an auto sync of generator be performed.

The Control Room SRO directs you to Place Unit 1 Main Generator Voltage Regulator in

service and Synchronize to the Grid per OP/l/A/6300/001 (Turbine Generator

StartuplShutdown) Encl. 4.1 (Automatic Mode Startup)

JPM OVERALL STANDARD: Unit 1 Main Generator Voltage Regulator in service and

L/ Synchronized to the Grid.

NOTES: Auto sync will not work, Manual sync will be required.

KA 062 A4.07 3.1/3.1

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-GEN-MG:205A

PAGE 3 OF 11

'u'

START TIME

STEPS ELEMENTS STANDARD SIU COMMENT!

REQUIRED

FOR UNSAT

-

1 Check Turbine speed Verifies turbine speed is

Jreater than 1710 rpm greater than 1710 rpm.

Cue:

Turbine speed indicates

1800 RPM

2 Check Voltage Regulator Verifies Voltage

aligned for Control Room Regulator aligned for

3peration per one of the control room.

Following

u OAC graphic Cue:

MAINGEN

Voltage Regulator is

U1 Gen Voltage aligned for Control

Reg Local Control Room control.

Panel

MID2342 (U1 Gen

Voltage Reg in

Local Cabinet

Control )

3 Locally check closed: Operator dispatches NLO

ow to locally check

contactors closed.

I I I I

u

DENOTES CRITICAL

OP-MC-JPM-GEN-MG:205A

PAGE 4 OF 11

--

STEPS ELEMENTS STANDARD SIU cc

RE(

FOR

4 Check PMG voltage 120- Same

130 VAC

Cue:

PMG voltage indicates

128 VAC

5 Check one of the Same

Following:

MID2348(Ul Cue:

Voltage Regulator

System) is normal MID2348 (U1 Voltage

Regulator System)

Trouble alarms or indicates normal

faults have been

reviewed on U1

Gen Voltage Reg

Local Control

Panel, on U1 Gen

Voltage Reg CH 1

Panel and U1 Gen

Voltage Reg CH 2

Panel

6 Znsure Voltage Regulator Same

n-MAN

Cue:

Switch selected to

MAN and MAN light

is lit

~

7 lepress ON for Same

!xcitation

Cue:

Excitation ON light Lit

and Exciter trip

annunciator cleared

DENOTES CRITICAL

OP-MC-JPM-GEN-MG:205A

PAGE 5 OF 11

-

STEPS ELEMENTS STANDARD s/u COMMENT

REQUIRED

FOR UNSAT

8 Check Generator voltage Operator checks OAC or

22.4 - 23.2 KV main control board

indications.

Cue:

Generator voltage

indicates 22.8 KV

9 Note: READY may take Same

15 - 90 seconds to

illuminate after excitation

breakers are closed.

Check lit Ready on Cue:

Voltage Regulator

READY light lit

IO -If auto Voltage Regulator Recognize from the Initial

operation is desired, Conditions that Auto sync

ensure Voltage Regulator of Generator was

in AUTO requested. Voltage

Regulator must be in

AUTO for Auto sync

capability (per Caution

prior to step).

Cue:

AUTO selected and

AUTO light LIT

11 -If manual Voltage Operator N/As step and

Regulator operation is proceeds.

desired.. .. ...

u

DENOTES CRITICAL

OP-MC-JPM-GEN-MG:205A

PAGE 6 OF 11

-

STEPS ELEMENTS STANDARD SIU COMMENT

REQUIRED

FOR UNSAT

12 Depress and hold Same

SYNC on either

Generator Breaker 1 A

or Generator Breaker Cue:

1B

Pushbutton depressed

and held

I2 Adjust Station Run Volts Same

slightly higher than

Note to evaluator:

Generator Incoming

Volts Using Voltage This step is only critical if

Adjust adjustments are required.

Cue:

Station Run Volts is

indicating slightly

higher than Generator

Incoming Volts

13 Release SYNC Same

Cue:

SYNC released

14 Notify System Engineer Same

Exciter Field is flashed

Cue:

Engineer notified

DENOTES CRITICAL

OP-MC-JPM-GEN-MG:205A

PAGE 7 OF 11

STEPS ELEMENTS STANDARD SIU COMMENT

REQUIRED

- FOR UNSAT

15 Close Generator MODs

as follows

Ensure Generator Cue:

Frequency is

greater than 59.6 Frequency indicates 60

HZ Hi!

If local operation of Cue:

MODs required,

perform Enc1.4.5 Local operation is not

required.

If Control Room operation

of MODs required,

perform the following:

Close

o MODsfor Cue:

Generator

Breaker 1A Pushbutton depressed,

red light lit

. o MODsfor Cue:

Generator

Pushbutton depressed,

Breaker 1B

red light lit

Dispatch operator Cue:

to locally check

MODs closed and NLO reports MODs

condensation in closed and no

the IPB enclosures :ondensation present.

DENOTES CRITICAL

OP-MC-JPM-GEN-MG:205A

W

PAGE 8 OF 11

-

STEPS ELEMENTS STANDARD SIU COMMENT

REQUIRED

FOR UNSAT

16 Notify SOC unit to be Phone call made

paralleled.

I7 Ensure Lit Valve Position Same

-imit Display

Cue:

Valve Position Limit

Display Button

depressed and lit

I8 -ewer limit to 17% using Same

Valve Position Limit

Cue:

-owe?

Valve position limit

lowered to 17% on

i/ Variable Display

window

19 f auto sync required, Recognize per Initial

Jetform the following Conditions that Auto sync

is required

Place Gen Switch placed in Auto

Auto/Man Sync 1 A or Auto 1B.

Select to Auto

1 A or Auto 1B

Cue:

Switch placed to

AUTO 1A (IB).

ow

U

DENOTES CRITICAL

OP-MC-JPM-GEN-MG:205A

PAGE 9 OF 11

STEPS ELEMENTS STANDARD COMMENT:

REQUIRED

FOR UNSAT

19 CONTINUED

If selected Selected breaker will not

generator breaker close, proceeds to next

fails to close, step.

depress Auto Cue:

Sync on DEH

panel. Breaker did not close.

Auto Sync depressed

on DEH panel. Breaker

does not close.

Cue:

Auto Sync depressed

on DEH panel. Breaker

does not close.

If selected breaker Cue:

does not close in 5

Five minutes have

minutes Repeats

elapsed.

steps 3.13.4.1 -

3.13.4.2 for

opposite breaker.

Cue:

Steps 3.13.4.1 - 3.13.4.2

repeated for opposite

breaker. It does not

close

If any Generator Cue:

breaker fails to

System Engineer has

close in 5 minutes, been informed.

notify System

Enaineer

20 Place Gen AutolMan Cue:

Sync Select in MAN

Switch placed to MAN

DENOTES CRITICAL

OP-MC-JPM-GEN-MGZ~O~A

PAGE 10 OF 11

STEPS ELEMENTS STANDARD COMMENT:

REQUIRED

FOR UNSAT

21 f manual sync of

lenerator is required,

ierform the following:

Obtain permission

from system

Engineer for

manual sync

Depress and hold Cue:

"SYNC for

"SYNC" depressed and

breaker to be

held

closed

Adjust Generator Synchroscope moving

slowly in the "FAST

speed until

Synchroscope direction. If not Turbine

hand moves slowly Generator speed

in "FAST" adjusted to obtain

direction. condition.

Cue:

Synchroscope moving

slowly in the fast

direction

Ensure "Station Cue:

Run Volts" slightly "Station Run Volts" is

higher than indicating slightly

"Generator higher than "Generator

Incoming Volts" Incoming Volts"

Using Voltage

Adjust

DENOT i CRITICAL

OP-MC-JPM-GEN-MG:205A

PAGE 11 OF 11

STEPS ELEMENTS STANDARD SIU COMMENT!

REQUIRED

- FOR UNSAT

21 ZONTINUED

When Synchroscope Selected breaker closed

indicates within 5 at 5 minutes before 12

minutes before 12 oclock on the

oclock position Synchroscope.

depress CLOSE for

selected breaker until

CLSD is lit.

Cue:

Pushbutton depressed,

red light lit

1 Release SYNC Cue:

SYNC released.

22 EN Generator Cue:

iaralleled to Grid, load

enerator as follows.. .

The SRO has directed

another operator to

load the Generator and

continue in this

procedure.

STOP TIME

DENOTES CRITICAL

INITIAL CONDITIONS

You are the Unit 1 Balance of Plant (BOP).

Unit 1 is being maintained between 12% and 15% RTP per OP/1/A/6100/003 (Controlling

Procedure for Unit Operation) Encl. 4.1 (Power Increase) by another Reactor Operator.

All Initial Conditions and steps in OP/1/A/6300/001 (Turbine Generator Startup/Shutdown)

Encl. 4.1 (Automatic Mode Startup) have been completed up to step 3.1 1

System Engineer has requested an auto sync of generator be performed.

The Control Room SRO directs you to Place Unit 1 Main Generator Voltage Regulator in

service and Synchronize to the Grid per 0P/l/N6300/001 (Turbine Generator

StartuplShutdown) Encl. 4.1 (Automatic Mode Startup)

SIMULATOR OPERATIONAL GUIDELINES

1. Reset to IC-I23

2. Insert OVR-MGOI7A

3. Insert OVR-MGOI7B

4. Acknowledge all alarms

5. Freeze Simulator

Enclosure 4.1 OP/~/A/6300/001

Automatic Mode Startup Page 1 of 15

'd

1. Limits and Precautions

1.1 Turbine shall be rotating prior to admitting steam.

1.2 Vacuum should be maintained during shutdown, except in an emergency.

1.3 Operate within startup, loading, or capability curves except in an emergency.

1.4 WHEN Turbine load less than lo%, maximum Low Pressure Turbine Steam Inlet

Temperature is 400°F.

1.5 WHEN Turbine load greater than IO%, maximum Low Pressure Turbine Steam Inlet

Temperature is 550°F.

1.6 Maximum condenser backpressure is 3.5 inches Hg when below 354 MWE (30%).

1.7 Maximum Bearing Oil Discharge Temperature is 180°F.

1.8 Minimum Bearing Oil Temperature is 70°F.

1.9 Maximum bearing metal temperatures is 225°F.

1.10 Maximum Delta T between the base and cover metals of High Pressure Turbine is

100°F.

1.11 Maximum allowed Turbine Vibration is 14.0 mils (16.0 mils for #11 Bearing).

1.12 Maximum allowed Turbine shaft eccentricity is 3 mils.

1.13 Maximum Generator Cold Gas Temperature is 48°C (1 18.4'F).

-

1.14 Concurrent operation of Bearing Oil/Seal Oil Backup Pump and Emergency Bearing Oil

Pump is prohibited.

1.15 Maximum Hz cooler warm gas temperature is 176°F (80°C)

1.16 MODS are manually operated in wrong direction or past normal open / closed

position, damage can occur to limit switches.

Unit 1

Enclosure 4.1 OP/1/A/6300/001

Automatic Mode Startup Page 2 of 15

ii

2. Initial Conditions

NOTE: Either Initial Condition 2.1 Initial Conditions 2.2 - 2.17 must be met.

-2.1 Entering procedure from PT/l/A/4250/004C (Turbine OPC and Mechanical Overspeed

Trip Test).

-OR

2.2 The following valve checklists have been completed

-- OP/l/A/6250/006 (Main Steam System)

Date

-- OP/l/B/6250/004 (Feedwater Heater Vents, Drain and Bleed System)

Date

- - Valves have been opened in Enclosure 4.4 (Startup Vent Valve Checklist) of

Date OP/l/B/6250/004 (Feedwater Heater Vents, Drain and Bleed System)

2.3 The following support systems are in service:

__- Turbine Lube Oil System (OP/l/B/6300/007)

Dale

i/

__- Main Turbine Hydraulic Oil System (OP/l/B/6300/008)

Date

-- Condensate and Feedwater Systems (OP/l/A/6250/001)

Date

__- Generator Stator Cooling Water System (OP/l/B/6300/002)

Date

__- Generator Seal Oil System (OP/l/B/6300/004)

Date

-- Generator Hydrogen System (OP/1/B/6300/003)

Date

-

-- Steam Seal System (OP/l/B/6300/005)

Date

-- Main Vacuum & Vacuum Priming System (OP/l/B/6300/006)

Date

- -0 Isolated Phase Bus Cooling System (OP/l/B/6300/010)

Date

- -2.4 IAE has completed PT/O/A/4250/004G (Turbine Trip Reactor Trip Operational Test)

Datc prior to rolling turbine.

- -2.5 Both Generator MODS open.

oate

Unit 1

Enclosure 4.1 OP/1/N6300/00I

Automatic Mode Startup Page 3 of 15

u

__- 2.6 Both Generator Breakers are open.

Date

2.7 One of the following:

__- 2.7.1 MlS0121 (Gen Reg Supply Brkr) indicates open.

Date -

- -2.7.2 "FCB OFF" is lit on U1 Gen Voltage Reg Local Control Panel.

Date

- -2.8 "Gen Auto/Man Sync Select" in "MAN".

Dale

- -2.9 Turbine Drain Valves in "AUTO'.

Date

-__ 2.10 Generator Neutral Disconnects locked closed.

Date

- -2.11 Turbine Supervisory Instruments in Control Room and at Turbine Panel are in service.

Date

- -2.12 Turbine Rotor-to-Casing differential expansion is within limits per recorder.

Date

- -2.13 "Exh Hood Spray" in "AUTO".

Dare

_.- 2.14 Governor Valves in "Single Valve" mode.

3ate

L/

_ _ _ _ 2.15 "EXCITATION" is "OFF".

Date

- -2.16 Ensure all Generator Lockouts are reset.

Date

_ _ _ _ 2.17 Turbine Generator has been rotating 4 continuous hours.

Date

3. Procedure

0 3.1 Evaluate all outstanding R&Rs that may impact performance of this procedure.

-

3.2 E entering this procedure after performing PT/l/N4250/004C (Turbine OPC and

Mechanical Overspeed Trip Test), go to Section 3.10.

0 3.3 Record highest reading LP Turbine inlet metal temperature from OAC Points MlA0389,

MlA0395, and MlA0401. OF

__ 3.4 E any Governor Valve or Throttle Valve position indicates less than -0.8% or more than

2%, notify System Engineer.

-__ /

Person Contacted Date Time

Unit 1

Enclosure 4.1 OP/1/A/6300/00 1

Automatic Mode Startuv Page 4 of 15

0 3.5 Maintain LT lube oil temperature per OP/l/B/6300/007 (Turbine Lube Oil System).

3.6 Latch Main Turbine as follows:

3.6.1 Check:

0 "Turbine Tripped"

0 "Megawatt Xducer" - Good

0 "OPC Press Xducer" - Good

0 "IMP Press Xducer" - Good

0 "Impulse Loop" - Out

0 "Megawatt Loop" - Out

3.6.2 Check:

0 Intercept and Reheat Stop Valve lights indicate closed

0 Throttle Valve positions indicate -0.8 - 2%

0 Governor Valve positions indicate -0.8 - 2%

3.6.3 Zero Power Physics Test to be performed, isolate LH to Throttle Valves.

IAE

3.6.3.1 Ensure Throttle Valves will remain closed during Zero Power

'U'

IAE Physics Test.

Unit 1

Enclosure 4.1 OP/1/A/6300/001

Automatic Mode Startup Page 5 of 15

-3.6.4 Ensure lit "Valve Position Limit Display".

3.6.5 Depress "Valve Position Limit Lower" until "Variable Display" indicates 0%.

0 3.6.6 Check "0000" in both "Reference" and "Demand".

3.6.7 Page plant personnel to stand clear of Turbine while latching.

NOTE Turbine latching may take up to 30 seconds following long shutdown periods.

3.6.8 Depress and hold "Latch" until lit.

-3.6.9 Depress "Operator Auto".

3.6.10 Check

0 Intercept and Reheat Stop Valves open

0 Throttle and Governor Valves closed

3.6.1 1 Ensure lit "Valve Position Limit Display".

ii 3.6.12 Depress "Valve Position Limit Raise" until "VarL.- Display" indicates

120%.

0 3.6.13 Check Governor Valves full open.

3.6.14 Test trip mechanism of Governor, Intercept, and Reheat Stop Valves as

follows:

3.6.14.1 Operate trip mechanism manually or with solenoid.

0 3.6.14.2 Check all valves close freely.

-3.6.14.3 Depress and hold "Latch" until lit.

0 3.6.14.4 Check valves return to full open.

3.6.15 greater than 7 days since last test of "Overspeed Protection Control",

perform "Overspeed Protection Control (OPC) Test" per PT/l/A/4250/004I

(Pre-Startup Turbine Testing).

0 3.6.16 Perform PT/l/B/4250/004B (Turbine Trip Device Test).

0 3.6.17 Return to Power Increase per OP/l/A/6100/003 (Controlling Procedure For

Unit Operation).

ii

Unit 1

Enclosure 4.1 OP/l/A/6300/00 1

Automatic Mode Startuq Page 6 of 15

3.7 Reset Main Turbine as follows:

0 3.7.1 Check IAE has performed TV/GV hot calibrations.

__ 3.7.2 Station NLO to place Turbine on Turning Gear within 5 minutes in event

SRO Turbine trips off of Turning Gear.

__ 3.7.3 Trip Main turbine.

__ 3.7.4 Ensure lit "Valve Position Limit Display".

__ 3.7.5 Depress "Valve Position Limit Lower" until "Variable Display" indicates 0%.

0 3.7.6 Check "0000" in both "Reference" and "Demand".

0 3.7.7 Page plant personnel to stand clear of Turbine while latching.

__ 3.7.8 Depress and hold "Latch" until lit.

__ 3.1.9 Depress "Operator Auto".

3.7.10 Check:

0 Intercept and Reheat Stop Valves open

0 Throttle and Governor Valves closed

__ 3.7.11 Ensure lit "Valve Position Limit Display".

__ 3.7.12 Depress "Valve Position Limit Raise" until "Variable Display" indicates

120%.

0 3.7.13 Check Governor Valves full open.

0 3.7.14 Return to Power Increase per OP/l/A/6 1001003 (Controlling Procedure For

Unit Operation).

Unit 1

Enclosure 4.1 OP/liA/6300/00 1

Automatic Mode Startuq Page 7 of 15

NOTE: This note applies any time Turbine is being accelerated.

Acceleration rate should be changed in stages when starting and approaching desire(

speeds.

Cold Start maximum acceleration rate is 75 rpdmin except in critical range.

(Greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months post trip)

Hot Start maximum acceleration rate is 100 rpdmin except in critical range. (Less

than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months post trip)

Shaft critical occurs at 900 - 1300 rpm.

Blade critical occurs 1650 - 1750 rpm.

Acceleration rate should be increased in critical ranges to 120 rpdmin.

Maximum acceleration rate is 120 rpdmin.

3.8 Roll Turbine to 680 rpm as follows:

__ 3.8.1 MSRs to be operated in manual, begin startup of MSRs per

OP/I/B/6250/011 (Moisture Separator Reheater Operation).

0 3.8.2 Record HP Turbine 1st stage Temperature (MlA0303). "F

3.8.3 Determine following per OP/I/A/6100/022 (Unit 1 Data Book):

SRO

Acceleration Rate rpdmin

- Loading Rate MW/min

3.8.4 Ensure Turbine Generator rolling on turning gear 4 continuous hours prior to

rolling turbine.

3.8.4.1 -

IF Turbine shaft at zero speed greater than 5 minutes during

4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months period, notify System Engineer.

-- /

Person Contacted Date Time

-3.8.5 Ensure LH restored to Throttle Valves.

IAE

3.8.6 Place "Turning Gear" in "MAN".

Enclosure 4.1 OP/1/A/6300/00 1

Automatic Mode Startup Page 8 of 15

0 3.8.7 Begin accelerating to 680 rpm per OP/l/A/6300/001A (Turbine-Generator

Load Change).

0 3.8.8 Check Turning Gear disengages and stops.

0 3.8.9 Check for unusual noises, rubs, and vibrations as Turbine accelerates.

3.8.10 Prior to turbine reaching 600 rpm, ensure "Bearing Lift Pump" in "AUTO".

3.8.1 1 WHEN Turbine reaches 600 rpm, ensure the following:

- Exhaust Hood Spray commences

__ "Bearing Lift Pump" stops

__ 3.8.12 WHEN Turbine rolling at 680 rpm, check

0 All supervisory instruments in Control Room

0 Locally for unusual noises and vibrations

0 Oil flow to all bearings

3.9 Accelerate Turbine to 1800 rpm per OP/l/A/6300/001A (Turbine-Generator Load

Change).

L

0 3.9.1 Check for unusual noises, rubs, and vibrations as Turbine accelerates.

3.10 WHEN Turbine at 1800 rpm, perform the following:

3.10.1 @greater than 7 days since performing PT/l/A/4250/0041 (Pre-Startup

Turbine Testing), perform the following:

0 3.10.1.1 Test "Overspeed Trip Device Test" per PT/l/A/425010041(Pre-

Startup Turbine Testing) (SLC 16.7.5).

0 3.10.1.2 Test "Manual Turbine Trip Test" per PT/l/A/4250/0041 (Pre-

Startup Turbine Testing) (SLC 16.7.5).

-3.10.2 Ensure Turbine at 1800 rpm.

3.10.3 Ensure only one of the following running:

- 1ALHPump

-

1BLHPump

Unit 1

Enclosure 4.1 OP/1/M63 OO/OO 1

Automatic Mode StartuQ Page 9 of 15

L-'

3.10.4 Ensure in "AUTO":

- 1ALHPump

__ 1BLHPump

__ 3.10.5 WHEN displays match actual Turbine speed and Turbine speed has stabilized

at 1800 rpm, depress "TRANSFER TV-GV".

0 3.10.5.1 Check transfer occurs by observing valve position indicators.

__ 3.10.6 Stop Bearing Oil Pump/GSOB Pump.

3.10.7 Place "Bearing Oil Pump/GSOB Pump" in "AUTO"

0 3.10.8 Check MIA0874 (Unit 1 Seal Oil Hydrogen D/P) is 12 -14 psid.

0 3.10.9 Adjust LG temperature per OP/l/B/6300/004 (Generator Seal Oil System).

3.1 1 Place Voltage Regulator in service as follows:

0 3.11.1 CheckTurbine speed greater than 1710 rpm.

'b 0 3.1 1.2 Check Voltage Regulator aligned for Control Room operation per one of the

following:

OAC Graphic "MAINGEN'

U1 Gen Voltage Reg Local Control Panel

MlD2342 (U1 Gen Volt Reg In Local Cabinet Control)

3.11.3 Locally check closed

IEGB-SX-Q701 (U1 Gen Voltage Reg Ch 1 Discon)

0 lEGB-SX-Q702 (U1 Gen Voltage Reg Ch 2 Discon)

3.11.4 Check PMGvoltage 120 - 130 VAC.

3.11.5 Check one of the following:

0 MlD2348 (U1 Gen Voltage Regulator System) is normal

17 G u b l e alarms or faults have been reviewed on the following:

U1 Gen Voltage Reg Local Control Panel

U1 Gen Voltage Reg Ch 1 Panel

U1 Gen Voltage Reg Ch 2 Panel

Unit 1

Enclosure 4.1 OP/1/A/6300/001

Automatic Mode Startup Page 10 of 15

i/

3.11.6 Ensure Voltage Regulator in "MAN".

3.1 1.7 Depress "ON" for Excitation.

0 3.1 1.8 Check Generator Voltage 22.4 - 23.2 KV.

NOTE: "READY" may take 15 - 90 seconds to illuminate after Excitation Breakers are closed.

0 3.11.9 Check lit "READY" on Voltage Regulator.

CAUTION: Gen Voltage Reg Control must be in "AUTO" for Autosync capability.

I

-3.1 1.10 E auto Voltage Regulator operation is desired, ensure Voltage Regulator in

"AUTO".

3.11.11 E manual Voltage Regulator operation is desired, perform the following:

0 3.1 1.11.1 Maintain Generator parameters within Capability Curve 3.1.1 or

Capability Curve 3.1.2 of OP/I/A/6100/022 (Unit 1 Data Book).

-3.1 1.11.2 Ensure "MAN" on Voltage Regulator.

3.11.1 1.3 E unit online or will be placed online, notify SOC that Voltage

Regulator is in manual. (Dispatcher Phone or 704-382-4413)

~- i

Person Contacted Date Time

3.11.12 Depress and hold "SYNC" on either "Generator Breaker 1A"

or "Generator Breaker 1B".

3.11.13 Adjust "Station Run Volts" slightly higher than "Generator Incoming Volts"

using Voltage Adjust.

~ 3.11.14 Release "SYNC".

3.11.15 Notify System Engineer that Exciter field has been flashed.

SRO

-- /

Person Contacted Date Time

Unit 1

Enclosure 4.1 OP/1/A/6300/001

Automatic Mode Startup Page 11 of 15

3.12 Close Generator MODS as follows:

3.12.1 Ensure Generator Frequency greater than or equal to 59.6 Hz.

__ 3.12.2 E local operation of MODS is required, perform Enclosure 4.5 (Local

Operation Of Generator Breaker MODs).

3.12.3 E Control Room operation of MODS is required, perform the following:

3.12.3.1 Close:

__ MODs for Generator Breaker 1A

__ MODS for Generator Breaker 1B

3.12.3.2 Dispatch operator to locally check

0 MODSclosed for Generator Breaker 1A

0 MODS closed for Generator Breaker 1B

Ji No condensation in IPB enclosures through windows at

MODs

Unit 1

Enclosure 4.1 OP/1/A/6300/001

Automatic Mode Startup Page 12 of IS

3.13 Synchronize Generator to grid as follows:

3.13.1 Notify SOC (System Operation Center) unit to be paralleled. (382-4413 or

dispatcher phone)

3.13.2 Ensure lit "Valve Position Limit Display".

__ 3.13.3 Lower limit to 17% using "Valve Position Limit Lower".

NOTE: Voltage Regulator in "MAN, manual sync of generator is required. 1

3.13.4 auto sync of generator is required, perform the following:

"Auto Sync" being depressed.

-3.13.4.1

Select" in "Auto 1A" or "Auto IB", the selected

generator breaker will close if generator frequency and voltage match system without

Place "Gen Auto/Man Sync Select" to "Auto 1A" or "Auto IB".

I

W,'

3.13.4.2 -

IF selected generator breaker failed to close, depress "Auto

Sync" on DEH panel.

__ 3.13.4.3 -

IF selected generator breaker fails to close in 5 minutes, repeat

Steps 3.13.4.1 -3.13.4.2 for opposite breaker.

-3.13.4.4 -

IF any generator breaker failed to close in 5 minutes, notify

System Engineer.

-- I

Person Contacted Date Time

3.13.4.5 Place "Gen AutoiMan Sync Select" in "Man".

Unit 1

Enclosure 4.1 O P i l /A/63 OO/OO 1

Automatic Mode Startup Page 13 of 15

-3.13.5 E manual sync of generator is required, perform the following:

__ 3.13.5.1 Obtain permission from System Engineer to perform manual sync

of generator breakers.

__- /

Person Contacted Date Time

-3.13.5.2 Depress and hold "SYNC" for breaker to be closed.

NOTE: Synchroscope should be moving less than 1 revolution in 20 seconds.

-3.13.5.3 Adjust Generator speed until Synchroscope hand moves slowly in

"FAST" direction.

__ 3.13.5.4 Ensure "Station Run Voltage" is slightly higher than "Gen

Incoming Voltage" using "Voltage Adjust".

__ 3.13.5.5 WHEN synchroscope indicates within 5 minutes before 12

o'clock position, depress "CLOSE" for selected breaker until

"CLSD" is lit.

'W

__ 3.13.5.6 Release "SYNC".

-3.13.6 WHEN Generator paralleled to grid, load Generator as follows:

3.13.6.1 Maintain Pwr Fact to 0.90 - 0.95 Lag using "Voltage Adjust"

__ 3.13.6.2 Depress "MW IN".

- 3.13.6.3 Ensure lit "Valve Position Limit Display".

-3.13.6.4 Raise limit to 120% using "Valve Position Limit Raise".

__ 3.13.6.5 Check "Demand" and "Reference" windows match actual load.

0 3.13.6.6 Load Turbine to 25 MWE per OP/l/A/6300/001A (Turbine-

Generator Load Change).

Unit 1

Enclosure 4.1 OP/l/A/6300/001

Automatic Mode StartuQ Page 14 of 15

3.13.7 Place other Generator Breaker in service as follows:

3.13.7.1 Depress and hold "SYNC" for selected breaker.

-3.13.7.2 WHEN Synchroscope for selected breaker in 12 o'clock position,

depress "CLOSE" for selected breaker until "CLSD" light is lit.

3.13.7.3 Release "SYNC".

0 3.14 Load Turbine to 120 MWE per OP/1/A/6300/001A (Turbine-Generator Load Change).

3.15 Perform the following while continuing with unit startup:

0 3.15.1 Maintain air temperature out of Exciter Air Cooler at 90 - 115°F by throttling

1KR-178 (Exciter Air Cooler Throttle). {PIP 00-0867)

3.15.2 Place "Turb Dm Vlvs Cntrl" in "AUTO".

3.15.3 Place in "AUTO":

-0 ISM-78 (A SM line Drain)

__ 1SM-84 (B SM Line Drain)

__ ISM-90 (C SM Line Drain)

- ISM-96 (D SM Line Drain)

0 3.15.4 Check open all piston operated check valves per Enclosure 4.4 (Valve

Checklist).

3.15.5 E MSR Control System is in "SYSTEM MANUAL", open all piston

operated check valves using red "OPEN" pushbutton.

-3.15.6 Reset Generator Core Monitor alarm.

Unit 1

Enclosure 4.1 OP/1/A/6300/001

Automatic Mode Startuq Page 15 of 15

3.15.7 Adjust Generator Core Monitor flow to obtain a 90% output current reading

on Core Monitor chart and local meter as follows:

~ 3.15.7.1 Adjust flow on Generator Core Monitor to establish local meter

indication of 90% using valve at bottom of flow meter

(5000 cclmin).

I NOTE: Generator speed, internal temperature, and pressure affect flow rate. I

0 3.15.7.2 Check flow rate and meter indication after one hour and adjust

flow to 90% on local meter.

-3.15.7.3 meter indication drifts to less than 90%, adjust flow rate per

Step 3.15.7.1 to retum meter indication to 90%.

3.15.8 Check following level controllers in "A" with setpoint of "0":

0 lHW-l6(1Al CWCFHPHtrNormDmCntrl)

0 1HW-17 (1A2 CWCF HP Htr Norm Dm Cntrl)

0 IHW-18 (1A3 CWCF HP Htr Norm Drn Cntrl)

0 1HW-31 (1B1 CWCF HP Htr Norm Dm Cntrl)

0 1HW-32 (1B2 CWCF HP Htr Norm Dm Cntrl)

0 1HW-33 (1B3 CWCF HP Htr Norm Drn Cntrl)

0 1HW-100 (1D1 CWCF LP Htr Norm Dm Cntrl)

0 lHW-lOl(lD2 CWCF LP Htr Norm Drn Cntrl)

0 1HW-102 (1D3 CM/CF LP Htr Norm Drn Cntrl)

0 IHW-l15(1EI CM/CFLPHtrNormDmCntrl)

0 1HW-116 (1E2 CM/CF LP Htr Norm Drn Cntrl)

0 1HW-117 (1E3 CM/CF LP Htr N o m Dm Cntrl)

. 0 1HW-130 (1F1 CWCF LP Htr Norm Drn Cntrl)

0 1HW-131 (1F2 CWCF LP Htr Norm Dm Cntrl)

0 1HW-132 (1F3 CWCF LP Htr Norm Dm Cntrl)

3.15.9 1_F Dual Tower H2 Dryer in service, place in "OFF".

- Tower 1 Adsorb Blwr

- Tower 2 Adsorb Blwr

End of Enclosure

Unit 1

OP-MCJPM-ECC-NI:116A

PAGE 1 OF 14

Prepared By:

U Reviewed By:

/

Approved By:

TASK: Align the ND, NI, and NV Systems to Cold Leg Recirculation

POSITION: RO

Operator's Name

Location: Simulator Method: Perform

Estimated JPM Completion Time: 2 Minutes

Actual JPM Completion Time: - Minutes

ii

The JPM Operator's performance was evaluated against the standards of this JPM and is

determined to be:

SATISFACTORYNNSATISFACTORY (circle one)

Evaluator's Signature Date 1 1

-.

References: EP/I/Af5000/ES-l .3 Transfer to Cold Leg Recirc

EPll lA/5000/E-1 Loss of Reactor or Secondary Coolant

JPM verified current with references by

Date I /

Rev. 13104-14-03

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-ECC-NI:116A

PAGE 2 OF 14

ii INITIAL CONDITIONS

You are the Unit 1 Balance of Plant (BOP) Operator.

,J

Unit 1 has experienced a large break LOCA inside containment. J

i

EP/l/A/5000/E-0 has been completed. /

/

EP/I/A/5000/FR-P.l (Response to Imminent Pressurized Thermal Shock) and

EP/I/A/5000/FR-Z.l (Response to High Containment Pressure) has been implemented to

address existing CSF orange paths. \ - /

EP/I/A/5000/E-l (Loss of Reactor or Secondary Coolant) is currently in effect and has

been completed through Step # 14.

The SRO directs you to continue in EP/l/A/5000/E-1 (Loss of Reactor or Secondary

Coolant), beginning with Step #15.

ii JPM OVERALL STANDARD: Upon receiving the FWST Level Lo annunciators, the operator

transitions to EP/l/A/5000/ES-I .3 (Transfer to Cold Leg Recirc)

per foldout page of E-lor Step 15.b RNO. Atrain of ND and

both trains of NI and NV are then aligned to Cold Leg Recirc.

NOTES: This JPM is designed to be performed as a SIMULATION or as

a WALKTHROUGH. Cues found in shaded boxes should be

given to the trainee for either setting.

KA 006 A4.07 4.4/4.4

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-ECC-NI:116A

PAGE 3 OF 14

u

START TIME

IC- ELEMENTS

Check transfer to Cold

Leg Recirc criteria:

STANDARD

NOTE: Operator uses

control board indications

to check equipment

tatus. Operator

.ansitions to ES-1.3

,hen FWST LEVEL LO

innunciator is received

expected to come in

-

COMMENTS

REQUIRED

-OR UNSAT

vhile performing the first

hree steps of this JPM.

UA any steps in E-I not

letformed after the

ransition to ES-1.3)

i_/

3perator checks FWST

FWST level -

eve1 indications at

LESS THAN 180

approximately 200 inches

INCHES (FWST

LEVEL LO and proceeds to RNO.

ALARM)

Cue:

FWST level gages

indicate 200 inches

RETURN TO Same

Step 13.

W

-

DENOTES CRITICAL

OP-MC-JPM-ECC-N1:116A

PAGE 4 OF 14

ELEMENTS STANDARD COMMENT:

TEPS

REQUIRED

-OR UNSAT

2 iitiate evaluation of ;ame

lant status:

heck Cold Leg Recirc

2pability:

ny ND pump - he:

VAILABLE 30th ND pumps have

ndication of power and

low

lower to following valves

AVAl LABLE

IND-19A (A ND Xe:

Pump Suct From 'ower is available.

FWST or NC)

INI-185A (RB Cue:

SUMP To Train A Power is available.

ND & NS)

1ND-58A (Train A Cue:

ND to NV & NI Power is available.

Pumps)

IND-4B (B ND Cue:

Pump Suct From Power is available.

FWST or NC)

-

DENOTES CRITICAL

OP-MC-JPM-ECC-N1:116A

PAGE 5 OF 14

-

STEPS ELEMENTS STANDARD SIU COMMENTS

REQUIRED

FOR UNSAT

2 :ONTINUED Same

INI-184B (RB :ue:

SUMP To Train B Jower is available.

ND & NS)

INI-136B (B NI he:

Pump Suction sower is available.

From ND)

INI-332A (NV & NI Cue:

Pumps Suction X- Power is available.

over)

INI-333B (NV & NI Cue:

Pumps Suction X- Power is available.

over)

INI-334B (NV & NI Cue:

Pumps Suction X- Power is available.

over Blk)

INI-147A (NI Cue:

Pumps Miniflow Power is available.

Hdr Isol)

1NI-I 15B (A NI Cue:

Pump Miniflow) Power is available.

INI-144B (B NI Cue:

Pump Miniflow) Power is available.

DEN01 i CRITICAL

OP-MC-JPM-ECC-NI:116A

PAGE 6 OF 14

STEPS ELEMENTS STANDARD s/u COMMENT:

REQUIRED

FOR UNSAT

-

2 CONTINUED

S LATCHED on Same

ollowing switches - LIT

1NI-1848 control Cue:

permissive for Switch is LIT

recirc mode

1NI-I 85A control Cue:

permissive for Switch is LIT

recirc mode

heck aux bldg radiation: Operator checks EMFs

for TriplTTrip2 lights or

checks associated EMF

Annunciators - dark.

All area monitor Cue:

EMFS- NORMAL All area monitor EMFs

-

indicate NORMAL

EMF-41 (AUXBldg Cue:

Ventilation) - EMF41 (Aux Bldg

NORMAL Ventilation) indicates -

NORMAL

WHEN the TSC is Cue:

staffed, THEN...

Consult station Cue:

management to start

The OSM is consulting

additional plant

equipment to assist in station management.

recovery as necessary.

I

DENOTES CRITICAL

OP-MC-JPM-ECC-NI:116A

PAGE 7 OF 14

STEPS ELEMENTS STANDARD s/u COMMENT

REQUIRED

FOR UNSAT

-

3 Check if NC System Operator determines NC

cooldown and pressure is not greater

depressurization is than 286 PSlG and

required: proceeds to the RNO.

NC pressure - GREATER Cue:

THAN 286 PSlG NC pressure indicates

15 PSlG

ND flow to cold legs Cue:

greater than 500 GPM, ND flow to cold legs is

THEN GO TO Step 15. greater than 500 GPM.

4 Respond to FWST Operator transitions to

LEVEL LO annunciators. EP/I/A/5000/1.3

(Transfer To Cold Leg

Recirc.) per the foldout

page of E-I or Step 15. b

RNO.

Cue:

FWST LEVEL LO

annunciators have just

illuminated

5 Have STA monitor foldout Same

page

Cue:

The STA will monitor

the foldout page

DENOTES CRITICAL

OP-MCJPM-ECC-NI:116A

PAGE 8 OF 14

STEPS ELEMENTS STANDARD COMMENT

REQUIRED

FOR UNSAT

6 Perform this EP without Same

delay. CSF procedures

should not be

implemented until

directed by this

procedure.

7 Check containment sump Operator checks sump

level - GREATER THAN level indications (behind

3 FT. ND section of main

control boards) to verify

level is greater than 3 ft.

Cue:

Containment sump

level indications read 8

feet.

8 Check KC flow to ND Operator checks KC to

heat exchangers - ND heat exchanger flow

GREATER THAN 5000 indications (behind ND

GPM. section of main control

I boards) to verify flow is

greater than 5000 GPM

to each heat exchanger.

Cue:

KC to ND heat

exchanger flow

indications both read

greater than 5000 GPM.

DENOTES CRITICAL

OP-MC-JPM-ECC-NI:116A

PAGE 9 OF 14

-

STEPS ELEMENTS STANDARD SIU COMMENT!

REQUIRED

FOR UNSAT

9 teset the following: Operator ensures SI1 and

Sequencers reset for

both trains.

SI1 Cue:

RESET light illuminated

Cue:

RESET light illuminated

Sequencers Cue:

RESET light illuminated

Cue:

RESET light illuminated

10 Align ND System for

recirc:

Check INI-185A Same

(RB Sump To

Train A ND & NS) Cue:

- OPEN

Red light is lit

Check 1A ND Same

Pump - O N

Cue:

Red light is lit

DENOTES CRITICAL

0P-MC-JPM-ECC-NI:I 16A

PAGE 10 OF 14

-

STEPS ELEMENTS STANDARD s/u COMMENT,

REQUIRD

FOR UNSAT

10 CONTINUED

Check INI-184B Operator determines that

(RB Sump To 1NI-I 84 is closed and

Train B ND & NS) proceeds to the RNO

- OPEN

Cue:

Green light is lit

Perform the following: Same

Place control Cue:

permissive in

Bypass and 0, Bypass selected on

1NI-1848 INI-1846. Pushbutton

depressed. Green light

is lit. Red light is dark.

IF INI-184B is Operator determines that

opening, THEN valve is not opening and

--

GO TO Step 6.d proceeds to RNO 6.C.3

Cue:

Green light is lit. Red

light is dark.

-

IF INI-1848 is Cue:

closed, THEN

Green light is lit. Red

light is dark.

DENOTES CRITICAL

OP-MC-JPM-ECC-NI:I16A

PAGE 11 OF 14

jTEPS ELEMENTS STANDARD COMMENTS

REQUIRED

FOR UNSAT

10 :ONTINUED

;top 1B ND Pump Same

he:

'ushbutton depressed,

green light is lit

20 TO Step 6.e. Same

Enable power Same

disconnect and

close 1FW-27A Cue:

(FWST Supply To

Switch rotated

ND)

Clockwise

Pushbutton depressed,

green light is lit

Check any ND Same

pump-ON.

Cue:

1A ND pump is Of.

11 Align NV and NI Systems

for recirc:

Check NC Same

pressure - LESS

THAN 1600 PSlG Cue:

Gage indicates 15 PSlG

DENOTES CRITICAL

OP-MCJPM-ECC-NI:IlGA

PAGE 12 OF 14

- ~

ELEMENTS STANDARD s/u COMMENTS

jTEPS

REQUIRED

FOR UNSAT

11 ZONTINUED IOTE:It is critical to

lose either 1NI-147A

Close the )oth I N I - 1 1 5 B d INI-

following: 1448 in the following

teps.

I NI-I 158 (A NI Pump he:

vliniflow)

'ushbutton depressed,

areen light is lit

INI-144B (B NI Pump %e:

Vliniflow)

3ushbutton depressed,

jreen light is lit

Enable power Same

disconnect and

close 1NI-147A Cue:

(NI Pumps

Miniflow Hdr Isol) Switch rotated

clockwise

Pushbutton depressed,

green light is lit

Close the following Same

valves:

1NDSOA (Train A Cue:

ND TO Hot Leg

Isol) Pushbutton depressed,

green light is lit

IND-15B (Train B Cue:

ND To Hot Leg

Isol) Pushbutton depressed,

green light is lit

DENOTES CRITICAL

OP-MC-JPM-ECC-N1:116A

PAGE 13 OF 14

iTEPS ELEMENTS STANDARD COMMENT:

REQUIRED

FOR UNSAT

11 EONTINUED

Same

rlign ND train discharges

3 NI and NV pump

,uctions:

heck INI-334B (NV & Cue:

d l Pumps Suct X-Over

Red light is illuminated

Uk) - OPEN

)pen the following: Opening either 1NI-332A

or 1NI-333B satisfies the

c%ical part of this step.

INI-332A (NV & NI Cue:

Pumps Suction X-

Pushbutton depressed,

Over)

red light is lit

INI-333B (NV & NI Cue:

Pumps Suction X-

Over) Pushbutton depressed,

red light is lit

3pen the following: Same

- 1ND-58A (Train A Cue:

ND To NV & NI

Pumps) Pushbutton depressed,

red light is lit

INI-136B (B NI -Note: INI-136B will not

Pump Suction open due to being

From ND) interlocked with

INI-184B.

Cue:

Pushbutton depressed,

green light is lit

DENOTES CRITICAL .

OP-MC-JPM-ECC-N1:116A

PAGE 14 OF 14

STEPS ELEMENTS STANDARD COMMENT2

REQUIRED

FOR UNSAT

11 >ONTINUED

solate FWST from NV Same

and NI pumps:

Inable power disconnect Cue:

and close 1NI-I OOB

FWST TO NI Pumps) Switch rotated

clockwise

Pushbutton depressed,

green light is lit

Close the following: Same

1NV-221A (NV Pumps Cue:

Suct From FWST)

Pushbutton depressed,

green light is lit

1NV-222B (NV Pumps Cue:

Suct From FWST)

Pushbutton depressed,

green light is lit

12 Check if NS should be

aligned for recirc as Cue:

follows.. . Another operator has

been directed to

continue in this

-

STOP TIME

DENOTES CRITICAL

INITIAL CONDITIONS

You are the Unit 1 Balance of Plant (BOP) Operator.

Unit 1 has experienced a large break LOCA inside containment.

EP/l/A/5000/E-O has been completed.

EP/I/A/5000/FR-P.l (Response to Imminent Pressurized Thermal Shock) and

EP/I/A/5000/FR-Z.l (Response to High Containment Pressure) has been implemented to

address existing CSF orange paths.

EP/l/A/5000/E-I (Loss of Reactor or Secondary Coolant) is currently in effect and has

been completed through Step # 14.

The SRO directs you to continue in EP/l/N5000/E-1 (Loss of Reactor or Secondary

Coolant), beginning with Step #15.

ii

'b'

SIMULATOR OPERATIONAL GUIDELINES (Nkl16A)

1. Reset Simulator to IC-I24

2. Insert LOA -N1024 Racked in

3. Insert LOA-N1025 Racked in

4. Insert LOA-DG003 Stop D/G

5. Insert LOA-DGOO4 Stop DIG

6. Freeze the Simulator

7. Go to RUN when operator is ready to begin.

(RM-01)

Duke Power Company (1) ID No. EP/l/A15000/ES-1.3

PROCEDURE PROCESS RECORD Revision No. 016

PREPARATION

(2) Station

(3) Procedure Title

McGuire Nuclear Station

Transfer To Cold Leg Recirc

I ~ ~ OiLY~ ~ ~ ~

~~~ ~

(4) PreparedBy Weiner,Michael R // /J- Date October 3,2002

(5) Requires NSD 228 Applicability Determination? If Applicability Determinationis required, attach NSD 228 documentation

[ill Yes (New procedureor revision with major changes)

0 No (Revision with minor changes)

0 No (To incorporate previo sly a proved changes)

(6) Reviewed By S L (w ;Date

/ ; ;(/

Cross-DisciplinaryReview By (QR) NA Date

Reactivity Mgmt. Review By (QR) N& Date dq oz/

Mgmt. Involvement Review By (OPS Supt.) NA& Date l O ~ / ~ C '

(7) Additional Reviews

Reviewed By Date

(8) TemporaryApproval (ifnecessay)

BY (OSM/QR) Date

BY (w Date

(9) Approved By /R* Date 1Lbt/4L-

PERFORMANCE(Compare with ControlCopy every 14 calendar days while work is being performed.)

(10) Compared with Control Copy Dale

Compared with Control Copy Date

(11) Date(s) Performed

Work OrderNumber (WO#)

COMPLETION

(12) Procedure Completion Verification

0 Yes 0 NA Check lists and/or blanks initialed, signed, dated, or filled in NA. as appropriate?

0 Yes 0 NA Required enclosures attached?

0 Yes 0 NA Data sheets attached, completed, dated and signed?

0 Yes 0 NA Charts, graphs, etc. attached. dated, identified, and marked?

0 Yes 0 NA Procedure requirementsmet?

Verified By Date

(13) Procedure CompletionApproved Date

(14) Remarks (Aftach additional pages, if necessay)

Form based on NSD 703 App 0(Pmcedum Pmess Record

MNS TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/I/N5000/ES-1.3 1 of 19

UNIT 1 Rev. 16

A. Purpose

This procedure provides the necessary instructions for transferring the Safety Injection

System and Containment Spray System to the recirculation mode.

8. SvmDtoms or Entrv Conditions

This procedure is entered from:

EP/l/A/5000/E-I (Loss Of Reactor Or Secondary Coolant), Step 15, on low FWST level.

EP/I/N5000/ECA-2.1 (Uncontrolled Depressurization Of All Steam Generators), Step 12,

on low FWST level.

Other procedures whenever FWST level reaches the switchover setpoint.

MNS TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/l/A/5000/ES-1.3 2of 19

UNIT 1 Rev. 16

, I I I I

I A C T I O N / E X P E C T E D RESPONSE I I RESPONSE NOT O B T A I N E D I

C. Operator Actions

- 1. Have STA monitor foldout page.

- 2. Perform this EP without delay. CSF

procedures should not be implemented

until directed by this procedure.

- 3. Check containment sump level - Perform the following:

GREATER THAN 3 FT.

- a. LE NS has actuated during this event,

THEN GO TO Step 4.

---

- b. IF a tornado- LOCA outside

containment is known to have occurred,

--_

THEN GO TO Enclosure 2 (Loss of

NC or FWST Inventory Outside

Containment).

- 4. Check KC flow to each ND heat Perform the following:

-

exchanger GREATER THAN 5000 GPM.

a. Close:

- 1KC-50A (Trn A Aux Bldg Non Ess

sup Isol)

- 1KC-538 (Trn B Aux Bldg Non Ess

sup Isol).

b. Open:

- 1KC-56A (KC TO A ND Hx)

- 1 KC-81B (KC TO B ND Hx).

5. Reset the following:

- a. SA. a. Perform the following:

- 1) Dispatch operator to open reactor

trip breakers.

- 2) Reset SA.

- b. Sequencers b. Dispatch operator to open breaker for

affected sequencer DC control power:

- A Train 1EVDA Breaker 6

- B Train 1 EVDD Breaker 8.

I

EP/l/A/5000/ES-1.3

UNIT 1

I

TRANSFER TO COLD LEG RECIRC

I

PAGE NO.

40f19

Rev. 16 I

I1

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

I

6. Align ND System for recirc:

- a. Check 1NI-l85A (RB Sump To Train A a. Perform the following:

ND & NS) -OPEN.

- 1) Place control permissive in "Bypass"

and open 1NI-l85A.

- 2) E 1NI-l85A is opening, THEN GO

To Step 6.b.

3) E 1NI-185A is closed, THEN:

- a) Stop 1A ND Pump.

- b) Step 6.c.

- b. Check 1A ND Pump - ON. - b. Start 1A ND Pump.

- c. Check 1NI-1846 (RB Sump To Train B c. Perform the following:

ND & NS) - OPEN.

- 1) Place control permissive in "Bypass"

and open 1NI-1846.

- 2) IF 1NI-1848 is opening, THEN GO

-

TO Step 6.d.

3) E 1NI-l84B is closed, THEN:

- a) Stop 1 B ND Pump.

- b) GOTO Step 6.e.

- d. Check 1B ND Pump - ON. - A. Start 1B ND Pump

- e. Enable power disconnect and close

1FW-27A (FWST Supply TO ND).

TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/l/A/5000/ES-I .3 5 0 f 19

Rev. 16

UNIT 1

ACTION/EXPECTEO RESPONSE RESPONSE NOT OBTAINEO 1

6.(Continued)

- f. Check any ND pump - ON. f. both ND pumps are off, THEN

perform the following:

1) E both NS pumps are on,

containment pressure is less than

15 PSIG, THEN stop one NS pump

as follows:

- a) On train to be stopped, reset

Containment Spray.

- b) Stop one NS pump.

NOTE If

EP/l/A/5000/FR-Z.1

(Response To High

Containment

Pressure) is required,

it may be completed

as time allows.

- 2) EP/I/A/500O/F-O (Critical Safety

Function Status Trees) may now

be implemented.

- 3) CO To EPll/A/5000/ECA-1.1

(Loss Of Emergency Coolant

Recirc).

7. Align NV and NI Systems for recirc:

- a. Check NC pressure - LESS THAN - a. Stop NI pumps

1600 PSIG.

b. Close the following:

- INI-1158 (A NI Pump Miniflow)

- INI-144B (B NI Pump Miniflow)

- c. Enable power disconnect and close

INI-147A (NI Pumps Miniflow Hdr Isol).

MNS TRANSFER TO COLD LEG RECIRC PAGE NO.

EPIl /Al5000lES-1.3 6of 19

UNIT 1 Rev. 16

A C T I O N / E X P E C T E D RESPONSE I RESPONSE NOT O B T A I N E D

7. (Continued)

d. Close the following valves:

- 1ND-30A (Train A ND To Hot Leg

Isol)

- 1ND-158 (Train B ND To Hot Leg

Isol).

e. Align ND train discharges to NI and NV

pump suctions:

- 1) Check 1NI-334B (NV & NI Pumps - 1) Open valve.

Suet X-Obar Blk) - OPEN.

2) Open the following:

- 1NI-332A (NV & NI Pumps

Suction X-Over)

- 1Nl-3338 (NV & NI Pumps

Suction X-over).

3) Open the following:

- 1ND-58A (Train A ND To NV & NI

Pumps)

- 1NI-1368 (8 NI Pump Suction

- From ND).

f. Isolate FWST from NV and NI pumps:

- 1) Enable power disconnect and close

1NI-1008 (FWST To NI Pumps).

2) Close the following:

- INV-221A (NV Pumps Suct From

FWST)

- 1NV-222B (NV Pumps SuCt From

FWST).

MNS TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/ 1/N5000/E S - 1.3 7 o f 19

Rev. 16

UNIT 1

8. Check if NS should be aligned for recirc

as follows:

- a. Check "FWST LEVEL LO-LO alarm - a. Perform the following:

LIT.

CAUTION Steps to reset

Containment

Spray and

stop NS

pumps must

be completed

. within 45

seconds of

receiving

"FWST Level

LO-LO" alarm.

This step

applies even

after leaving

this EP.

1 WHEN "FWST LEVEL LO-LO"

alarm setpoint (33 inches) is

reached, THEN immediately

perform the following:

- a) Reset Containment Spray.

- b) Stop 1A NS Pump.

- c) Stop 1B NS Pump.

- d) Perform Steps 8.e through 8.h.

- 2) Ensure this step is flagged and crew

prepared to perform it immediately

upon receiving alarm.

- 3) Step 9.

- b. Reset Containment Spray.

- c. Stop 1A NS Pump.

- d. Stop 1B NS Pump.

.

MNS TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/l/A/5000/ES-1.3 80f19

Rev. 16

UNIT 1

A C T I O N i E X P E C T E D RESPONSE I RESPONSE NOT O B T A I N E D

8. (Continued)

- e. Check 1A NS Pump -AVAILABLE TO - e. GOTO Step 8.9.

RUN.

f. Align A Train NS to containment sump

as follows:

- 1) Check 1NI-l85A (RE Sump To Train - 1) G O m S t e p 8.9.

A ND & NS) -OPEN.

- 2) Close 1NSQOA (A NS Pump Suct - 2) GOTO Step 8.9.

From FWST).

- 3) Wait for 1NS90A to close. - 3) 1NS-20A remains open or

intermediate for over 30 seconds,

_

THEN _GO__ TO Step 8.9.

- 4) Open 1NS-18A (A NS Pump Suct - 4) GOTO Step 8.9.

From Cont Sump).

- 5).. Check "NS SYS CPCS TRAIN A - 5) GOTO Step 8.9.

INHIBIT" status light (13-12) -

DARK.

- 6) Start 1A NS Pump. - 6) Step 8.9.

- 7) Open 1RN-134A (A NS Hx Inlet - 7) GO TO Step 8.9.

Isol).

- 8) Throttle open 1RN-I37A (A NS Hx

Outlet Isol) to establish 3800 GPM

to 1A NS Hx.

MNS TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/l/N5000/ES-1.3 9of19

UNIT 1 Rev. 16

I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1

8. (Continued)

g. Align B Train NS to containment sump

as follows:

- 1) Check 1NI-l84B (RB Sump To Train - 1) GOTOStep 8.h

B ND & NS) - OPEN.

- 2) Close 1NS-3B (6 NS Pump Suct - 2) GOO Step 8.h

From FWST).

- 3) Wait for 1NS-36 to close. - 3) 1NS-36 remains open or

intermediate for over 30 seconds,

---

THEN GO TO Step 8.h.

- 4) Open 1NS-16 (6 NS Pump Suct - 4) =TO Step 8.h.

From Cont Sump).

- 5) Check "NS SYS CPCS TRAIN B - 5) m T O S t e p 8.h

INHIBIT status light (1SI-12) -

DARK.

- 6 ) Start 16 NS Pump. - 6) GOTO Step 8.h.

- 7) Open 1RN-2356 (6 NS HX Inlet - 7) GOTO Step 8.h.

Isol).

- 8) Throttle open 1RN-2386 (B NS Hx

Outlet Isol) to establish 3100 GPM

to 16 NS Hx.

-

- h. Check both NS pumps - ON h. Perform the following:

- 1) any NS pump is isolated from

containment sump, THEN dispatch

operator to pull control power fuses

on affected NS pump to prevent it

from starting with inadequate

suction.

- 2) IF AT ANY TIME the idle NS

pump@)can be started, S"

ensure proper a l i g n m e n t m

Step 8.f or 8.9 as required.

1

TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/l/A/5000/ES-I.3 10 of 19

Rev. 16

UNIT 1

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

9. Check if ND aux spray is required:

- a. Containment pressure - GREATER a. Perform the following:

THAN 3 PSIG.

- 1) IF AT ANY TIME containment

pressure goes above 3 PSIG, AND

both trains of ND aux spray are

closed, THEN perform Step 9

- 2) G O m S t e p I O .

b. Check the following: b. Perform the following:

- Time after reactor trip - GREATER 1) Ensure operator has been

THAN 50 MINUTES dispatched to remove tags and

close breakers for the following

At least one of the following - valves:

ENERGIZED:

- IEMXA-R2A ( I A ND TOA&B

- INI-l73A(TrainANDToA&B Cold Legs Cont Outside lsol

CL) Motor (INI-173A)) (aux bldg, 750,

FF-54, FF-55)

- IEMXBI-6B ( I B ND TO C&D NC

- INI-178B (Train B ND To C & D Cold Leg Cont Outside Is01 Motor

CL). (INI-1788)) (aux bldg, 733,

GG-55, GG-56).

- 2) Designate someone to notify crew

when 50 minutes from reactor trip

have elapsed.

CAUTION This step applies

even after

leaving this EP.

- 3) WHEN at-least one valve energized,

AND time after reactor trip is greater

than 50 minutes, THEN perform

Step 9.

- 4) Step 10.

MNS TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/l/A/5000/ES-1.3 11 of 19

Rev. 16

1 I I I I

A C T I O N / E X P E C T E D RESPONSE

I RESPONSE NOT O B T A I N E D

9. (Continued)

c. Check if core cooling can be maintained c. Check ND train status:

with minimum S/I flow:

- 1) E both ND trains are a l i g n e d m

- At least one NV pump - ON operating in Cold Leg R e c i r c , U

_

GO _TO Step 9.d.

- At least one NI pump - O N

- 2) W m S t e p 10.

At least one of the following valves -

OPEN:

- 1NI-9A (NC Cold Leg lnj From NV)

- 1NI-lOB (NC Cold Leg lnj From

NV).

d. Establish ND aux spray from one train

that is in Cold Leg Recirc mode:

For A train:

- 1) Close 1NI-l73A (Train A ND To A

& B CL).

- 2) Open 1NS-43A (A ND To NS

Cont Outside Isol).

.

For B train:

- 1) Close 1NI-1788 (Train B ND To C

& D CL).

- 2) Open 1NS-38B (6 ND To NS

Cont Outside Isol).

MNS TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/l/N5000/ES-l 3 12 of 19

UNIT1 Rev 16

I A C T I O N l E X P E C T E D RESPONSE RESPONSE NOT O B T A I N E D

CAUTION Failure to stop ND aux spray when required may result in a negative

containment pressure.

- f. WHEN containment pressure less than

1 PSIG, THEN stop ND aux s p r a y m

Enclosure 4 (Securing ND Aux

Containment Spray).

- 10. IF AT ANY TIME a BIO signal occurs,

THEN restart S/I equipment previously

on.

MNS TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/I/A/5000/ES-1 3 130f19

UNIT 1 Rev. 16

ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

CAUTION 0 SA recirculation flow to NC System must be maintained at all times.

Aux Bldg radiation may be higher due to Cold Leg Recirc alignment.

11, . Check proper Cold Leg Recirc flow and

valve alignment as follows:

a. Check the following - CLOSED: - a. Close valves.

- 1ND-19A (A ND Pump Suct From

FWST or NC)

- 1ND-4B (B ND Pump Suct From

FWST or NC).

b. Check either NV pumps miniflow valve. b. Perform the following:

CLOSED:

- 1) 1NI-9A (NC Cold Leg lnj From

- 1NV-150B (NV Pumps Recirculation) NV) AND 1NI-1OB (NC Cold Leg Inj

From NV) closed, THEN raise

OR charging flow to 175 GPM (to

reduce D/P across the NV pump

- 1NV-151A (NV Pumps Recirculation) miniflow valves).

2) Close the following valves:

- 1 NV-150B (NV Pumps

Recirculation)

- 1NV-151A (NV Pumps

Recirculation).

3) 1NI-9A AND 1NI-IOB closed,

T":

- 0 Control charging flow between

60 GPM and 175 GPM.

- 0 Maintain cunrging flow above

60 GPM in all subsequent EPs to

ensure NV pump miniflow.

- 4) NV recirc path still open, THEN

contact station management to

evaluate sump water being pumped

to aux bldg tanks.

TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/l/A/5000/ES-I.3 14 of 19

Rev. 16

UNIT 1

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

11. (Continued)

c. Check the following valves - CLOSED: c. E accessible, THEN dispatch operator

to close valvek):, I

- INI-100B (FWST TO NI Pumps)

- INI-100B (Unit 1 midget hole, 716+2,

- INV-221A (NV Pumps Suct From "-53, 10 ft north of the end of

FWST) grating)

- INV-2226 (NV Pumps Suct From - INV-221A (aux bldg, 716+3, JJ-52,

FWST). wall 20 ft north of BW pumps)

- INV-222B (aux bldg, 716+7, JJ-52,

wall 20.ft north of BW pumps).

d. Check S/I flow: d. Perform the following:

- Check "NV PMPS TO COLD LEG 1) E at least one flow path from the

F L O W - FLOW INDICATED sump to the NC System can not be

established, perform the

- Check NI pumps - FLOW following:

INDICATED

- Check ND pumps - FLOW

INDICATED. If

EP/I/A/5000/FR-

Z . l (Response

To High '

Containment

Pressure) is

required, it may

be completed as

time allows.

- a) EP/I/A/5000/F-O (Critical

Safety Function Status Trees)

may now be implemented.

- b) GO To EP/1/A/5000/ECA-1.1

(Loss Of Emergency Coolant

Recirc).

- 2) Evaluate local actions to establish

maximum Cold Leg Recirc

capability.

I rl

II MNS TRANSFER TO COLD LEG RECIRC PAGE NO.

EP/l/N5000/ES-1.3 15 of 19

Rev. 16

ImIT1

~

I I 1

ACT I ON/ EXPECTED RESPONSE I RESPONSE NOT O B T A I N E D

I

11. (Continued)

e. Check the following - CLOSED: e. Perform the following:

- 1KC-50A (Trn A Aux Bldg Non Ess - 1) Ensure normal letdown is isolated

sup Isol)

2) Close valves:

- 1KC-1A (Tm A Aux Bldg Non Ess

Ret Isol) - a) 1KC-50A

- 1KC-536 (Trn B Aux Bldg Non Ess - b) IKC-IA.

sup Isol)

- C) 1KC-536

- 1KC-2B (Trn B Aux Bldg Non Ess

Ret Isol). - d) 1KC-2B

3) E normal letdown was in service at

time transfer to Cold Leg Recirc was

initiated, THEN notify station

management to evaluate the

following prior to aligning KC back

to aux bldg non-essential header:

- Potential for KC voiding in

letdown heat exchanger

- Locally isolating KC to letdown

heat exchanger.

- f. Check KC flow to ND Hxs - - f. Evaluate local actions to establish KC

ESTABLISHED. flow to ND train(s) in service.

- 12. EP/l/A15000/F-O (Critical Safety

Function Status Trees) may now be

implemented.

- 13. RETURN procedure and step in

effect.

OP-MC-JPM-PS-NC: 167-IA

PAGE 1 OF 5

Prepared By:

L/ Reviewed By:

Approved By:

TASK: Respond to a Pressurizer Pressure Instrument Failure

POSITION: ROlSRO

Operator's Name

Location: Simulator Method: Perform

Estimated JPM Completion Time : 5 Minutes

Actual JPM Completion Time: Minutes

L

The JPM Operator's performance was evaluated against the standards of this JPM and is

determined to be:

SATlSFACTORY/UNSATlSFACTORY (circle one)

Evaluator's Signature Date I I

-

References: AP/1lA/5500/11 Pressurizer Pressure Anomalies

JPM verified current with references by

Date I I

Rev. 01104-14-03

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-PS-NC:167-IA

PAGE 2 OF 5

INITIAL CONDITIONS

You are the Unit 1 Operator at the Controls (OATC).

The Unit 1 Balance of Plant Operator (BOP) is in the Work Control Center attending a 91-

01 briefing.

Unit 1 is operating at 100% power.

All systems and controls are in their normal configuration for this power level.

The Control Room SRO directs you to respond to any changing plant conditions.

JPM OVERALL STANDARD: Operator recognizes NC System pressure is decreasing and

performs the Immediate Actions of A P l l I . "BACKUP" control

channel 3/2 is selected and affected PZR PORV block valve is

isolated prior to getting a LOW PZR PRESSURE RX trip.

NOTES: The Instrument failure will be actuated per examiner's signal to

simulator runner.

KA 027 AA1.01 4.013.9

i/

FOR TRAINING PURPOSES ONLY

0P-MCJPM-PS-NC:I 674A

PAGE 3 OF 5

i/

START TIME

STEPS ELEMENTS STANDARD s/u COMMENT!

REQUIRED

FOR UNSAT

~~

I Multiple annunciators Operator responds by

actuate indicating a by performing the

PORV has opened and Immediate Actions of

Pzr. Pressure is rapidly AP/11 (Pressurizer

decreasing. Pressure Anomalies)

Check actual Prr Cue:

-

pressure HAS GONE

DOWN. Actual Prr Pressure is

2100 PSIG and going

down

2 Check all Pzr. Pressure Operator determines Pzr

channels - pressure Channel 1 has

failed HlGH and

INDICATING THE

SAME. proceeds to the RNO.

Cue:

Pzr pressure Channel 1

(one) indicates 2500

PSIG.

.

3 -

IF either controlling Operator places PZR

PRESS CTRL SELECT

channel is

malfunctioning, THEN switch to Channel 3/2

place PZR PRESS position.

CTRL SELECT switch

to backup channel. Cue:

Switch rotated

clockwise two (2)

positions.

DENOTES CRITICAL

OP-MC-JPM-PS-NC:167-IA

PAGE 4 OF 5

jTEPS ELEMENTS STANDARD SIU COMMEI

REQUIRE

- FOR UNSl

4 :heck Pzr. PORVs - 3perator determines that

JORV NC-34 is not

LOSED

losed, then proceeds to

he RNO.

Cue:

Red and green lights

are illuminated

Operator attempts to

5 erform the following:

close the PORV, but it

will not close. Operator

then closes the PORV

block valve.

Close PORVs Same

Cue:

Switch rotated to

close,

Red and green lights

are still illuminated

-

IF POR\ !dill nc Same

close, THEN close

affected PORV Cue:

isolation valve.

Switch rotated to

close position. Red

light is extinguished,

green light is LIT.

DENOTES CRITICAL

OP-MC-JPM-PS-NC:167-IA

PAGE 5 OF 5

-

ELEMENTS STANDARD SIU COMMENT$

TEPS

REQUIRED

FOR UNSAT

3perator verifies both

6 :heck Pzr spray valves

spray valves closed.

CLOSED

o

l!&: Due to system

jynamics and the amount

,f time it takes to reach

his step, the spray

rlalves may still be open.

If they are, the operator

should proceed to the

RNO and manually close

both spray valves.

Cue:

Green lights are LIT

-Note: When satisfied that

all Immediate Actions

have been performed, the

evaluator will terminate

this JPM by giving the

following cue:

Cue:

Another Operator will

continue in this AP.

STOP TIME

DENOTES CRITICAL

INITIAL CONDITIONS

You are the Unit 1 Operator at the Controls (OATC).

The Unit 1 Balance of Plant Operator (BOP) is in the Work Control Center

attending a 91-01 briefing.

Unit 1 is operating at 100% power.

All systems and controls are in their normal configuration for this power level.

The Control Room SRO directs you to respond to any changing plant conditions.

SIMULATOR OPERATIONAL GUIDELINES (NC-167-IA)

1. Reset the Simulator to IC-125

2. Ensure Pzr Pressure select switch is in the Channel 1-2 position.

3. Freeze the Simulator

4. Insert the following malfunctions:

XMT-NC038 PNC-5160 Pzr PRESS CH-1

Severity = 2500, Ramp = 5, Trigger = 1

MAL-NCOI28 PZR PORV or SAFETY VALVE 1NC-34A,

Severity = 30, Ramp = 5, Trigger = 1

5. Go to run

-

1

6. When directed by Examiner, activate the malfunctions.

6. Symptoms

Pzr pressure channel failed

Pzr pressure going down in an uncontrolled manner

Pzr pressure going up in a n uncontrolled manner

Any Pzr PORV o r spray valve failed open

"PZR PORV DlSCH HI TEMP" alarm

"PRT HI TEMP" alarm.

C. Operator Actions

Check actual Pzr pressure - HAS GONE _-- GO TO Step 15.

DOWN.

Check all Pzr pressure channels - - either controlling channel is

INDICATING THE SAME. malfunctioning, THEN place "PZR

PRESS CNTRL SELECT" switch to

backup channel.

-@ Check Pzr PORVs - CLOSED. Perform the following:

- a. Close PORVs

- b. PORV will not close, close

PORV isolation valve.

-@ Check Pzr spray valves -CLOSED. Perform the following:

- a. Close Pzr spray valve(s)

- b. IF AT ANY TIME a reactor trip occurs

AND spray valve still open, THEN stop

1A and 18 NC pumps.

OP-MC-JPM-IC-ENB:181-IA

PAGE 1 OF 10

Prepared By:

Reviewed By:

'-d

Approved By:

TASK: Respond to a Failure of Power Range Channel N-42

POSITION: RO

Operator's Name

Location: Simulator Method: Perform

Estimated JPM Completion Time: 15Minutes

Actual JPM Completion Time: __ Minutes

L' The JPM Operator's performance was evaluated against the standards of this JPM and is

determined to be:

SATISFACTORYIUNSATISFACTORY (circle one)

Evaluator's Signature Date I I

References: AP/1lA/5500116 Malfunction of Nuclear Instrumentation

APl1lA/550O/l4 Rod Control Malfunction

JPM verified current with references by

Date I I

Rev. 02104-10-03

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-IC-ENB:181-IA

PAGE 2 OF 10

b

INITIAL CONDITIONS

You are the Unit 1 Balance of Plant Operator (BOP).

Unit 1 was operating at 55% power with control rods at 120 steps Bank D, when PR N42

failed high causing rods to step in approximately 6 steps.

AP/l/A/5500/16 (Malfunction of Nuclear Instrumentation) Case 111 (Power Range

Malfunction) has been entered and completed through step 5.

The SRO directs you to perform steps 6 through 18 of AP/I/N5500/16 (Malfunction of

Nuclear Instrumentation, Case 111 (Power Range Malfunction).

JPM OVERALL STANDARD: Power Range Channel NI-42 is removed from service with

control power fuses removed. Tavg is restored to within 1

degree of Tref by adjusting control rods. Continuous rod motion

is recognized and the Immediate Actions of AP-14 (Rod

ii Control Malfunctions) are properly performed from memory.

The Reactor is manually tripped.

KA 015 A2.01 3.5/3.9

L,

OP-MC-JPM-IC-ENB:181-IA

PAGE 3 OF 10

W

START TIME

STEPS ELEMENTS

- Secure any power

1

icrease in progress

Same

he:

STANDARD

40 power increase is in

wogress

t COMMENTS

REQUIRED

FOR UNSAT

Jerform the following same

2

ictions at the

MISCELLANEOUS

2ONTROL AND

NDlCATlON PANEL"

drawer:

Place the he:

appropriate "ROD

STOP BYPASS Switch is rotated

switch to the failed counterclockwise one

channel position position

Place the Cue:

"POWER

MISMATCH Switch is rotated

BYPASS switch counterclockwise one

to the failed position

channel position

DENOTES CRITICAL

OP-MC-JPM-IC-ENB:18I-IA

PAGE 4 OF 10

ELEMENTS STANDARD COMMENT$

TEPS

REQUIRED

-OR UNSAT

~

erform the following Same

3

ictions at the

DETECTOR CURRENT

OMPARATOR drawer:

Place UPPER Cue:

SECTION defeat

switch to the failed Switch is rotated

channel position. counterclockwise one

position

Check the Cue:

CHANNEL

DEFEAT light for Light is lit.

the upper section -

LIT.

Place the LOWER Cue:

SECTION defeat

switch to the failed Switch is rotated

channel position. counterclockwise one

position

Check the Cue:

CHANNEL

DEFEAT light for Light is lit.

the lower section -

LIT.

DENOTES CRITICAL

OP-MC-JPM-IC-ENB:181-IA

PAGE 5 OF 10

-

STEPS ELEMENTS STANDARD SIU COMMENT:

REQUIRED

FOR UNSAT

4 Perform the following Same

actions at the

"COMPARATOR AND

RATE" drawer:

Place the Cue:

"COMPARATOR

CHANNEL Switch is rotated

DEFEAT" switch to counterclockwise one

the failed channel position

position.

Check the Cue:

"COMPARATOR

DEFEAT light - LIT. Light is lit.

NOTE: Removing fuses Operator removes the

5

from power range Control Power fuses for

drawers may cause N42, but does not

associated NIS remove the Instrument

annunciators to alarm. Power fuses for N-42.

Trip Bistables of failed Same

channel as follows:

Remove Control power Cue:

fuses from "POWER

RANGE A" drawer Fuses are rotated 118

turn counterclockwise

and removed

-IF Power Range Cabinet Cue:

shows evidence of

damage (Le. visual No smoke or abnormal

smoke or abnormal smell is apparent at the

smell), THEN remove

Instrument power fuses

from "POWER RANGE

B" drawer

DENOTES CRITICAL

OP-MC-JPM-IC-ENB:181-IA

PAGE 6 OF 10

STEPS ELEMENTS STANDARD COMMENTS

REQUIRED

FOR UNSAT

heck the following Same

6

tatus lights for the failed

hannel - LIT

"NUC he:

OVERPOWER .ight is illuminated

ROD STOP CH

l(1I,III,IV) B Y P

(ISI-19)

"PIR HI FLUX LO >ue:

STPT" (ISI-2) i g h t is illuminated

"P/R HI FLUX HI he:

STPT" (1SI-2) -ight is illuminated

"P/R HI FLUX Sue:

RATE" (1 SI-3)

Light is illuminated

7 Zheck the following

annunciator lights - LIT:

"P/R HI VOLTAGE Cue:

- FAILURE"

(IAD-2, F-3) Light is illuminated

"P/R HI FLUX HI Cue:

STPT ALERT" Light is illuminated

(IAD-2, A-3 )

"P/R HI FLUX Cue:

RATE ALERT"

Light is illuminated

(IAD-2, A-I).

DENOTES CRITICAL

OP-MC-JPM-IC-ENB:181-IA

PAGE 7 OF 10

NTEPS ELEMENTS STANDARD COMMENT:

REQUIRED

-OR UNSAT

8 :heck the following Same

tatus lights on

SI-I8 - LIT

PIR LO he:

SETPOINT TRAIN

A TRIP BLOCKED -ight is illuminated

PIR LO Cue:

SETPOINT TRAIN

B TRIP BLOCKED Light is illuminated

9 E desired to control SIG Same

wels in auto, THEN

Cue:

eturn affected SIG CF

ontrol valves to auto. SIG CF control valves

are in AUTO

3sure operable PIR Same

10

hannel selected to

,ecord on Nuclear Power Cue:

,ecorder

Switch positioned to

P-I (3,4)

Ydjust control rods to Note to evaluator:

I 1 Respond as CIR SRO if

naintain T-Ave at T-Ref.

permission to move rods

is requested. This step is

critical only if >I

degree

deviation between Tavg

and Tref.

Cue:

Rods are being moved

in MANUAL and

T-Ave is approaching T

Ref.

DENOTES CRITICAL

STEPS

I2

ELEMENTS

WHEN T-Avg within 1°F

of T-Ref AND auto rod

zontrol is desired,

return rods to auto

THEN

STANDARD

The Operator positions

rods until T-Avg is within

1"F of T-Ref, then returns

rods to "AUTO" after the

first cue is cliven.

Cue:

Automatic rod control

is desired.

When rod control switch

is placed in AUTO, the

rods will begin stepping

out at 72 steps/minute.

The Operator should

recognize this as an entry

+-

OP-MC-JPM-IC-ENB:181-IA

PAGE 8 OF 10

I

COMMENT!

REQUIRED

FOR UNSAT

condition of AP/14 (Rod

Control Malfunction) and

perform the Immediate

Actions from memory.

Cue:

Rods placed to AUTO,

rods are stepping out at

72 steps per minute,

Torbinelgenerator

output is stable

Turbine impulse

pressure, Tref, Power

Range Nl's, T-hot and

T-cold indications are

stable.

DENOTES CRITICAL

OP-MC-JPM-IC-ENB:181-IA

PAGE 9 OF 10

STEPS ELEMENTS STANDARD SIU COMMENT$

REQUIRED

FOR UNSAT

-

13 APlllAl5500114 Rod Operator determines no

Control Malfunction rods are dropped and

(Immediate Actions) proceeds to Step 2.

Operator places rods to

MANUAL. Rods continue

to step out. The Reactor

should be manually

tripped.

more than one rod Cue:

dropped, THEN:

Trip reactor No indications of a

dropped rod are

GOT0 present on DRPI screen

EPll IN5000lE-0

(Reactor Trip or

Safety Injection)

Place control rods in Cue:

manual.

Switch rotated

clockwise one position.

Check rod movement - Operator recognizes rods

STOPPED are not stopped and

proceeds to RNO.

Cue:

Rods are stepping out.

DENOTES CRITICAL

0P-MC-JPM-IC-ENB:I814A

PAGE 10 OF 10

-

ELEMENTS STANDARD SIU COMMENT5

TEPS

REQUIRED

FOR UNSAT

lperator manually trips

13 Continued ieactor and begins to

ierform Immediate

Yctions of E-0.

-

IF rod movement

continues, THEN

perform the following:

Trip reactor Cue:

GOT0 Reactor trip switches

EPllIN5000lE-0 rotated counter

(Reactor Trip or clockwise. All rod

Safety Injection) bottom lights are lit.

Green lights lit on both

Reactor trip breakers.

IIR amps going down.

Terminate JPM with the

following cue:

Cue:

The CR SRO has

directed another

operator to continue in

E-0.

STOP TIME

DENOTES CRITICAL

INITIAL CONDITIONS

c/

You are the Unit 1 Balance of Plant Operator (BOP).

Unit Iwas operating at 55% power with control rods at 120 steps Bank "D",

when PR N42 failed high causing rods to step in approximately 6 steps.

AP/I/A/5500/16 (Malfunction of Nuclear Instrumentation) Case 111 (Power Range

Malfunction) has been entered and completed through step 5.

The SRO directs you to perform steps 6 through 18 of AP/l/A/5500/16

(Malfunction of Nuclear Instrumentation, Case 111 (Power Range Malfunction).

, SIMULATOR OPERATOR GUIDELINES (ENB-181A)

L-1

1 Reset to IC-34, place Simulator to RUN and allow the plant to stabilize.

2 Insert Malfunction ENBOl3C set = 200%.

3 Allow rods to step in approximately ten steps, then place Rods in MANUAL

4 Place "PR To S/G Program Level Channel Defeat" switch to "Defeat PR 42 & 4 4

5 Acknowledge alarms, then FREEZE simulator

6 Insert Override OVR-IRE002A (CRD Bank Sel Sw Auto Pos) = OFF, set to trimer 1.

7 Insert Override OVR-IRE002B (CRD Bank Sel Sw Man Pos) = ON, set to triaqer 1.

8 Insert Override OVR-IRE003B (Full Length Rod Motion Sw Out Pos) = ON, set to

trimer 1.

9 Insert Malfunction MAL-IREO16A (Control Rod Speed Selection) = 72 Severity Value

and set to trimer 1.

i/. TEMP SNAP RESET TO IC-I26

10 Place simulator in RUN when examinee is ready to begin JPM.

11

When examinee places Rod Control back to AUTO per step 17 of the

procedure, Activate triclqer 1.

(R06-97)

Duke Power Company (1) ID No. AP/l/A/5500/16

PROCEDURE PROCESS RECORD Revision No. 7

PREPARATION

(2) Station McGuire Nuclear Station

INFORMATION ONLY

(3) Procedure Title Malfunction Of Nuclear Instrumentation

(4) Prepared By

c

3. *

(5) Requires 10CFR50.59 evaluation?

I

Date July 15,1999

[SI Yes (New procedure or revision with major changes)

0 No (Revision with minor changes)

No

(6) Reviewed By (OR)

Cross-DisciplinaryReview By (QR) N

Reactivity Mgmt. Review By (QR) &

Ne&

Q

%

.ta! 8/h?

(7) Additional Reviews

Reviewed By Date g//s/y7

Reviewed By Date

(8) Temporary Approval (if flecessa*

BY (SRO/QR) Date

BY (QR) Date

(9) Approved BY Date peg*%'

PERFORMANCE(Compare with Control Copy every 14 calendar days while work is being performed.)

(10) Comparedwith Control Copy Date

Comparedwith Control Copy Date

(11) Date@)Performed

Work Order Number (WO#)

-.

COMPLETION

(12) Procedure Completion Verification

Yes 0 N/A pheck lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?

0 Yes 0 N/A Listed enclosures attached?

0 Yes 0 N/A Data sheets attached, completed, dated and signed?

0 Yes 0 N/A Charts, graphs, etc. attached, dated, identified, and marked?

0 Yes 0 N/A Procedure requirementsmet?

Verified By Date

(13) Procedure Completion Approved Date

(14) Remarks (attach additionalpages, if necessary.)

MNS MALFUNCTION OF NUCLEAR INSTRUMENTATION PAGE NO.

AP/I/N5500/16 12 of 18

Case 111 Rev. 7

UNIT 1 Power Range Malfunction

ACTION/EXPECTED RESPONSE 1 RESPONSE NOT OBTAINED I

C. ODerator Actions

-0 Place rods in manual.

- 2. Check SIG levels - A T PROGRAMMED - Place affected SIG CF control valves in

LEVEL. manual and return level to programmed

level.

- 3. Announce occurrence on paging system.

MNS MALFUNCTION OF NUCLEAR INSTRUMENTATION PAGE NO.

AP/1/N5500/16 Case 111 1 3 O f 18

UNIT 1 Power Range Malfunction Rev. 7

I A C T I O N I E X P E C T E D RESPONSE RESPONSE NOT O B T A I N E D

I

- 4. Check PIR channels ONLY ONE - Perform the following:

CHANNEL FAILED.

- a. Initiate unit shutdown to Mode 3 within

one hour, as required by Tech Spec

3.0.3.

- b. REFER II!RP1O1N5700l010(NRC

Immediate Notification Requirements).

c. Ensure the following interlocks in proper

condition for existing plant conditions:

- P-IO Nuclear at Power

- . P-7 Lo Power Rx Trips Blocked

- P-8 Hi Pwr Lo Flo Rx Trip Blocked.

- d. RETURN To procedure in effect.

- 5. Position "PR TO 9 G PROGRAM LEVEL

CHANNEL DEFEAT" switch to defeat

inoperable channel.

- 6. Secure any power increase in progress.

7. Perform the following actions at the

-."MISCELLANEOUS CONTROL AND

INDICATION PANEL" drawer:

- a. Place the appropriate "ROD STOP

BYPASS" switch to the failed channel

position.

- b. Place the "POWER MISMATCH

BYPASS" switch to the failed channel

position.

MNS MALFUNCTIONOF NUCLEAR INSTRUMENTATION PAGE NO.

AP/llN5500/16 Case 111 140f 18

UNIT 1 Power Range Malfunction Rev. 7

I ACTION/EXPECTEO RESPONSE I RESPONSE NOT OBTAINED

8. Perform the following actions at the - Notify IAE.

"DETECTOR CURRENT COMPARATOR"

drawer:

- a. Place "UPPER SECTION" defeat

switch to the failed channel position.

- b. Check the "CHANNEL DEFEAT" light

for the upper section - LIT.

- c. Place the "LOWER SECTION" defeat

switch to the failed channel position.

- d. Check the "CHANNEL DEFEAT" light

for the lower section - LIT.

9. Perform the following actions at the - Notify IAE.

"COMPARATOR AND RATE" drawer:

- a. Place the "COMPARATOR CHANNEL

DEFEAT" switch to the failed channel

position.

- b. Check the "COMPARATOR DEFEAT"

light - LIT.

Removing fuses from power range drawers may cause associated NIS

annunciators to alarm.

10. Trip bistables of failed channel as

follows:

- a. Remove Control Power fuses from

'"POWER RANGE A" drawer.

- b. Power Range Cabinet shows

evidence of damage (Le. visual smoke

or abnormal smell), THEN remove

Instrument Power fuses from "POWER

RANGE 3 drawer.

MNS MALFUNCTION OF NUCLEAR INSTRUMENTATION PAGE NO.

AP/l/N5500/16 Case 111 15 01 18

UNIT 1 Power Range Malfunction Rev. 7

A C T l O h / E X P E C T E D RESPOElSE RESPONSE NOT O B T A I N E D

12. Check the following annunciator lights - - Notify IAE.

LIT:

- "P/R HI VOLTAGE FAILURE (IAD-2,

F-3)

- "P/RHI FLUX HI STPT ALERT" (IAD-2,

A-3)

- "P/R HI FLUX RATE ALERT" (1AD-2,

A-1).

13. Check the following status lights on Perform the following:

1SI-18 - L I T

- a. Check "P/R HI FLUX LO STPT ALERT"

- 0 "P/R LO SETPOINT TRAIN A TRIP alarm (1AD-2, A-2) - LIT.

-

BLOCKED" b. E alarm is dark, THEN notify IAE to

-

- "P/R LO SETPOINT TRAIN B TRIP investigate. -

BLOCKED.

- 14. E desired to control SIG levels in auto,

THEN return affected SJG CF control

valves to auto.

- 15. Ensure operable P/R channel selected to

record on NIS Recorder.

- 16. Adjust control rods to maintain T-Ave at

T-Ref.

_ -adjust

IF rods will not move in manual, MEN

turbine load to maintain T-Ave at

T-Ref.

MNS MALFUNCTION OF NUCLEAR INSTRUMENTATION PAGE NO.

AP/1/Al5500/16 160f 18

Case 111

Rev. 7

UNIT 1 Power Range Malfunction

I A C T I O N I E X P E C T E D RESPONSE f RESPONSE NOT O B T A I N E D

18. Instruct IAE to trip bistables associated

with failed P/R channel within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of

failure PER IP/O/A/3090/014 (Tripping

Inoperable Protection Channels):

- OPDT

- OTDT.

19. IF AT ANY TIME failed P/R channel is

repaired prior to IAE tripping bistables,

T":

- a. Inform IAE that bistables are no longer

required to be tripped.

- b. mmStep21.

20. WHEN IAE completes Step 18, THEN - Notify IAE.

check status lights for affected P/R - LIT

For P/R N-41:

-

. "NC LOOP A OPDT RX TRIP" (1 SI-7)

"NC LOOP A OTDT RX TRIP (ISI-7).

For PIR N-42:

- "NC LOOP B OPDT RX TRIP (1 SI-7)

- "NC LOOP B OTDT RX TRIP (1SI-7).

For PIR N-43:

- "NC LOOP C OPDT RX TRIP (ISI-7)

- "NC LOOP C OTDT RX TRIP" (ISI-7).

For PIR N-44:

-

"NC LOOP D OPDT RX TRIP (ISI-7)

"NC LOOP D OTDT RX TRIP (IS-7).

MNS MALFUNCTION OF NUCLEAR INSTRUMENTATION PAGE NO.

APl1lN5500116 170f 18

Case 111

UNIT 1 Power Range Malfunction Rev. 7

I A C T I O N l E X P E C T E O RESPONSE I RESPONSE NOT O B T A I N E D I

21. WHEN malfunctioningP/R channel

repaired, MEN perform the following:

- a. Ensure instrument power fuses in

"POWER RANGE B" drawer installed.

- b. Install control power fuses in "POWER

RANGE A" drawer.

- c. Select "RESET" on the "RATE MODE

SWITCH".

- d. Check reactor power - GREATER d. Perform the following:

THAN 25%.

1) Check the following bistable - '

DARK:

- "P/R HI FLUX LO STPT" (ISI-2).

- 2) E bistable lit, THEN notify IAE.

- 3) GOTO Step 21 .f.

e. Check the following bistable - LIT: - e. Notify IAE.

- "PIR HI FLUX LO STPT" (ISI-2).

f. Check the following bistables - DARK: - f. Notify IAE.

- "PIR HI FLUX HI STPT" (ISI-2)

- "P/R HI FLUX RATE" (1 SI-3).

- g. Place "COMPARATOR CHANNEL

DEFEAT" switch to "NORMAL".

- h. Place "POWER MISMATCH BYPASS

switch to "OPERATE".

- i. Place "UPPER SECTION" switch to

"NORMAL".

- j. Place "LOWER SECTION" switch to

"NORMAL".

- k. Place "ROD STOP BYPASS" switch to

"OPERATE".

MNS MALFUNCTIONOF NUCLEAR INSTRUMENTATION PAGE NO.

AP/1/A/5500/16 180f 18

Case 111

UNIT 1 Power Range Malfunction Rev. 7

ACTION/EXPECTED RESPONSE RESPONSE NOT O B T A I N E D

- I. Place "PIR TO SIG PROGRAM LEVEL

CHANNEL DEFEAT" switch to

"NORM".

rn. E IAE tripped bistables PER Step 18,

Z "perform the following:

1) Instruct IAE to place the following

bistables for failed channel back in

service:

- OPDT

- OTDT.

2) WHEN IAE has placed bistables - 2) Notify IAE.

back in service, THEN check status

lights for failed P/R - DARK:

For PIR N-41:

- "NC LOOP A OPDT RX TRIP

(ISI-7)

- w "NC LOOP A OTDT RX TRIP"

(ISI-7).

For P/R N-42:

- "NC LOOP E OPDT RX TRIP"

(ISI-7)

-e "NC LOOP B OTDT RX TRIP

(1SI-7).

For PfR N-43:

- "NC LOOP C OPDT RX T R I P

(ISI-7)

- "NC LOOP C OTDT RX TRIP"

(1%-7).

For PIR N-44:

- "NC LOOP D OPDT RX TRIP"

(ISI-7)

- "NC LOOP D OTDT RX TRIP

(1 SI-7).

OP-MC-JPM-PSS-RN:185

PAGE 1 OF 6

Prepared By:

Reviewed By:

Approved By:

TASK: RN Emergency Alignment after a Loss of All AC on Unit 2

POSITION: RO

Operator's Name

Location: Control Room Method: Walkthrough

Estimated JPM Completion Time: 30 Minutes

Actual JPM Completion Time: Minutes

L..,

The JPM Operator's performance was evaluated against the standards of this JPM and is

determined to be:

SATISFACTORYIUNSATISFACTORY (circle one)

Evaluator's Signature Date I I

References: EP/2/A/5000/ECA-0.0 Loss of All AC Power

JPM verified current with references by

Date I I

Rev. 02/04-16-03

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-PSS-RN:185

PAGE 2 OF 6

INITIAL CONDITIONS

You are the Unit 2 Balance of Plant Operator (BOP).

Unit 2 is operating at 100% power with Atrain in service, when a loss of all AC power

occurs.

The Control Room SRO has implemented EP/2/A/5000/ECA-0.0 (Loss of All AC Power).

Unit 2 ETA is de-energized.

The 2B DIG has just been started and the essential bus (2ETB) energized and loaded

per EP/2/A/5000/ECA-O.O, Enclosure 8 (Energizing 4160 V Bus with D/G).

Unit 1 is at 100% power with 1ETA and 1ETB energized from their normal power source.

L

The Control Room SRO directs you to perform EP/2/A/5000/ECA-0.0 Enclosure 21(RN

Emergency Alignment).

JPM OVERALL STANDARD: B Train RN is aligned to the SNSWP per Enclosure 21.

NOTES: The evaluator shall provide a copy of EP/2/A/5000/ECA-0.0,

Enclosure 21 (RN Emergency Alignment) upon request.

KA 008 A4.01 3.3/3.1

u

DENOTES CRITICAL

OP-MC-JPM-PSS-RN:185

PAGE 3 OF 6

i/

START TIME

STEPS ELEMENTS STANDARD COMMENT:

REQUIRED

FOR UNSAT

1 Check 2ETA - Operator determines from

ENERGIZED Initial Conditions that

2ETA is not energized.

Cue as appropriate.

Cue:

Undervoltage Status

lights are lit

GO TO step 5 Same

2 Check 2ETB - Operator determines from

Initial Conditions that

ENERGIZED

2ETB is energized.

ii

Cue as appropriate.

Cue:

Volt meter indicates

4160 volts,

Undervoltage Status

lights are dark

3 Open the following B

Train valves:

2RN-204B (B NV Pump Cue:

Cooler Sup Isol) Pushbutton depressed,

red light lit

ORN-9B (Train 1B & 2B Cue:

SNSWP Supply Pushbutton depressed,

red light lit

i/

DENOTES CRITICAL

OP-MC-JPM-PSS-RN:185

PAGE 4 OF 6

TEPS ELEMENTS STANDARD COMMENT

REQUIRED

FOR UNSAT

~~

CONTINUED

Cue:

2RN-188 (B RN Pump Red light lit

Suction Isol)

2RN-297B (Train B Ess Cue:

Hdr Ret Isol) Red light lit

ORN-152B (Train 1B & Cue:

28 Disch to SNSWP) Pushbutton depressed,

red light is lit

2RN-171B (B DIG HX Cue:

Inlet Isol) Red light is lit

4 Place 2RN-187B (B KC Cue:

Hx Inlet Isol) Mode

Select in auto Switch is in Auto

position

5 Close the following B

Train valves:

ORN-2B (Train 1A & 2A Cue:

RC Supply) Green light is lit

L DENOTES CRITICAL

OP-MC-JPM-PSS-RN:185

PAGE 5 OF 6

jTEPS ELEMENTS STANDARD COMMENT:

REQUIRED

FOR UNSAT

5 ZONTINUED

!RN-63B (AB Non Ess he:

?eturn lsol

'ushbutton depressed,

jreen light is lit

!RN-41 B (Train B To %e:

Jon Ess Hdr Isol) Sreen light is lit

lRN-279B (AB Vent Sys Zue:

ieturn Isol) Pushbutton depressed,

green light is lit

Cue:

3RN-11B (Train 1B & 28

LLI Supply) Pushbutton depressed,

green light is lit

ORN-15B (Train 1B & 2B Cue:

Supply X-Connect Green light is lit

Cue:

ORN-151B (Train 1B &

2B Disch X-Connect) Green light is lit

Cue:

ORN-5B (Train 1B & 2B

RC Supply) Green light is lit

Cue:

ORN-284B (Train 1B &

2B Disch To RC) Pushbutton depressed,

- green light is lit

ii

DENOTES CRITICAL

OP-MC-JPM-PSS-RN: 185

PAGE 6 OF 6

STEPS ELEMENTS STANDARD SIU COMMENT:

REQUIRED

FOR UNSAT

10 RETURN step in Operator terminates JPM.

effect in body of

procedure

STOP TIME

L

DENOTES CRITICAL

INITIAL CONDITIONS

You are the Unit 2 Balance of Plant Operator (BOP).

Unit 2 is operating at 100% power with Atrain in service, when a loss of all AC power

occurs.

The Control Room SRO has implemented EP/2/A/5000/ECA-0.0 (Loss of All AC Power).

Unit 2 ETA is de-energized.

The 2B DIG has just been started and the essential bus (2ETB) energized and loaded

per EP/2/A/5000/ECA-0.0, Enclosure 8 (Energizing 4160 V Bus with DIG).

Unit 1 is at 100% power with 1ETA and 1ETB energized from their normal power source.

b The Control Room SRO directs you to perform EP/2/A/5000/ECA-O.O Enclosure 20 (RN

Emergency Alignment).

c

MNS LOSS OF ALL AC POWER PAGE NO.

EP/2/A/5000/ECA-O.O 121 of 127

Enclosure 21 - Page 1 of 4 Rev. 17

UNIT 2 RN Emergency Alignment

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2. Open the following A train valves:

- 2RN-103A (A NV Pump Cooler Sup Isol)

- OPEN

- ORN-I48AC (Train 1A & 2A Disch To

RC) - OPEN

- 2RN-296A (Train A ESS Hdr Ret Isol) -

OPEN

- ORN-147AC (Train 1A & 2A Disch TO

RC) -OPEN

- ORN-13A (Train 1A & 2A LLI Supply) -

OPEN

i - 2RN-16A (A RN Pump Suction Isol) -

OPEN

- 2RN-70A (A D/G Hx Inlet Isol) - OPEN

- ORN-12AC (Train 1A & 2A LLI Supply) -

OPEN.

- 3. Place 2RN-86A (A KC Hx Inlet Isol) Mode

Select in auto.

MNS LOSS OF ALL AC POWER PAGE NO.

122 of 127

EP/2/A/5000/ECA-0.0 Enclosure 21 - Page 2 of 4 Rev. 17

UNIT 2 RN Emergency Alignment

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

- ORN3A (Train 1A & 2A RC Supply) -

CLOSED

- ORN-7A (Train 1A & 2A SNSWP Supply)

- CLOSED

- ORN-149A (Train 1A & 2A Disch to

SNSWP) - CLOSED

- ORN-I 50A (Train 1A & 2A Disch

X-Connect) - CLOSED

- ORN-14A (Train 1A & 2A Supply

X-Connect) - CLOSED

- 2RN-64A (AB Non Ess Return Isol) -

CLOSED

i - 2RN-43A (Train B To Non Ess Hdr Isol) -

CLOSED

- 2RN-299A (AB Vent Sys Return Isol) .

CLOSED.

I

.

MNS LOSS OF ALL AC POWER PAGE NO.

EP/2/A/5000/ECA-O.O 123of 127

Enclosure 21 - Page 3 of 4 Rev. 17

UNIT 2 RN Emergency Alignment

- 5. -

Check 2ETB ENERGIZED. - RETURN Step in effect in body of this

procedure.

6. Open the following B train valves:

- 2RN-2048 (8 NV Pump Cooler Sup Isol)

-OPEN

- ORN-98 (Train 1B & 28 SNSWP Supply)

- OPEN

- 2RN-18B (B RN Pump Suction Isol) -

OPEN

- 2RN-297B (Train B Ess Hdr Ret Isol) -

OPEN

- ORN-I52B (Train 18 & 28 Disch to

SNSWP) - OPEN

'i

- 2RN-171B (B D/G Hx Inlet Isol) - OPEN.

- 7. Place 2RN-187B (6KC Hx Inlet Isol)

Mode Select in auto.

MNS LOSS OF ALL AC POWER PAGE NO.

EP/2/AJ5000/ECA-0.0 Enclosure 21 - Page 4 of 4 124 of 127

Rev. 17

UNIT 2 RN Emergency Alignment

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. Close the following B train valves:

- ORN-2B (Train 1A & 2A RC Supply) -

CLOSED

- 2RN-63B (AB Non Ess Return Isol) -

CLOSED

- 2RN-41B (Train B To Non Ess Hdr Isol) -

CLOSED

- 2RN-279B (AB Vent Sys Return Isol) -

CLOSED

- ORN-I 1B (Train 1B 8.28 LLI Supply) -

CLOSED

- ORN-158 (Train 1B & 2B Supply

X-Connect) - CLOSED

- ORN-I51B (Train 1B & 28 Disch

X-Connect) - CLOSED

- ORN-58 (Train 1B & 28 RC Supply) -

CLOSED

- ORN-284B (Train 1B & 28 Disch To RC) -

CLOSED.

- 9. RETURN step in effect in body of this

procedure.

OP-MC-JPM-CNT-VUL:158

PAGE 1 OF 7

Prepared By:

ii Reviewed By:

Approved By:

TASK: Startup the Unit 2 Lower Containment Ventilation System

POSITION: RO

Operator's Name

Location: Control Room Method: Walkthrough

Estimated JPM Completion Time: -10 Minutes

Actual JPM Completion Time: - Minutes

L-

The JPM Operator's performance was evaluated against the standards of this JPM and is

determined to be:

SATISFACTORYIUNSATISFACTORY (circle one)

Evaluator's Signature Date I I

-.

References: 0P/2/A/6450/001 Containment Ventilation System

,JPM verified current with references by

Date I I

Rev. 01104-14-03

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-CNT-VUL:158

PAGE 2 OF 7

i/ INITIAL CONDITIONS

A Unit 2 NC system heat-up is in progress following a short outage.

The Lower Containment Ventilation System had been shutdown during the outage.

All initial conditions have been satisfied for OP/2/A/6450/001, Enclosure 4.2.

There are no outstanding R&Rs that will impact the performance of OP/2/A/6450/001,

Enclosure 4.2.

The SRO instructs the RO (YOU) to start the Unit 2 Lower Containment Ventilation System

per OP/2/A/6450/001, Enclosure 4.2. The SRO desires the following alignment:

Three (3) VL Fans(A, B, and C) in HIGH speed

One (1) Pipe Tunnel Booster Fan (A) in HIGH speed

All four (4) S/G Booster Fans (A, B, C, and D) ON

One (1) Pressurizer Booster Fan (A) ON

JPM OVERALL STANDARD: A, B, and C VL AHU's and the A Pipe Tunnel Booster Fan

L are running in "High" speed, all S/G Booster Fans ON and

Pressurizer Booster Fan A ON.

NOTES:

KA022000 A4.01 3.6/3.6

TASK: MO-3334

b

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-CNT-VUL:158

PAGE 3 OF 7

b

START TIME

STEPS ELEMENTS STANDARD COMMENT:

REQUIRED

FOR UNSAT

~

1 F the unit 2 in Modes Operator determines

I- 5, cooling water is from the initial conditions

3vailable to VL units per of the JPM that all

3P/OIA/6400/009 procedure initial

Containment Ventilation conditions are satisfied.

>ooling Water System)

~

!valuate all outstanding Operator determines

2

i&Rs that may impact from the initial conditions

ierformance of this of the JPM that R&Rs

xocedure. have been evaluated.

~

'erform the following Operator proceeds to

3

sections as applicable: Section 3.3.

Section 3.3, Starting VL

4HU's

~

4 Starting VL AHU's Same

Ensure

- in "AUTO"

2LCVU-D-1 (2A Cue:

VL AHU Suction

Damper Cntrl) Pushbutton depressed

2LCVU-D-2 (2B Cue:

VL AHU

Suction Damper Pushbutton depressed

Cntrl)

2LCVU-D-3 (2C Cue:

VL AHU

Suction Damper Pushbutton depressed

Cntrl)

DENOTES CRITICAL

OP-MC-JPM-CNT-VUL:158

PAGE 4 OF 7

STEPS ELEMENTS STANDARD SIU COMMENT$

REQUIRED

FOR UNSAT

ONTINUED

2LCVU-D-4 (2D Cue:

VL AHU

Suction Damper Pushbutton depressed

Cntrl)

rlOTE: "LOW" speed light

should be lit 7 seconds

after starting VL AHU.

Select "LOW for desired

JL AHU(s)

"2A VL AHU Mode Cue:

Select"

Switch is rotated

clockwise, red light lit

"2B VL AHU Mode Cue:

Select" Switch is rotated

clockwise, red light lit

"2C VL AHU Mode Cue:

Select"

Switch is rotated

clockwise, red light lit

"2D VL AHU Mode NIA

Select"

DENOTES CRITICAL

OP-MC-JPM-CNT-VUL:I 58

PAGE 5 OF 7

-

STEPS ELEMENTS STANDARD s/u COMMENT$

REQUIRED

FOR UNSAT

4 ZONTINUED

heck OPEN on Same

iperating VL AHU(s):

2LCVU-D-5 (2A Cue:

VL AHU Disch Lamp is illuminated

2LCVU-D-6 (2B Cue:

VL AHU Disch

Lamp is illuminated

2LCVU-D-7 (2C Cue:

VL AHU Disch

Lamp is illuminated

2LCVU-D-8 (2D NIA

VL AHU Disch

NOTE: VL AHU should Cue:

be allowed to operate in

LOW for 1 minute One minute has

minimum prior to elapsed.

selecting HIGH

desired to operate in Same

high speed, select

HIGH for operating VL

AHU(s):

2AVL AHU Mode Cue:

Select

Switch is rotated

clockwise, red light lit

2B VL AHU Mode Cue:

Select

Switch is rotated

clockwise, red light lit

DEN01 TCRITICAL

OP-MC-JPM-CNT-VUL:158

PAGE 6 OF 7

STEPS ELEMENTS STANDARD s/u COMMENT:

REQUIRED

FOR UNSAT

-

4 CONTINUED

2C VLAHU Mode Cue:

Select

Switch is rotated

clockwise, red light lit

2D VL AHU Mode N/A

Select

5 Starting Pipe Tunnel Operator starts the A

Booster Fan. Pipe Tunnel Booster Fan

Place one of the in HIGH speed, per the

following in HIGH: JPM Initial Conditions.

2A Pipe Tunnel Cue:

Booster Fan

Switch is rotated

-

OR clockwise, red light lit

2B Pipe Tunnel N/A

Booster Fan

-

IF neither fan is Operator N/As step and

- available for high proceeds.

speed operation.. ...

Check OPEN for

operating fan:

2PTBF-D-I(2A Cue:

Pipe Tunnel Bstr

Lamp is illuminated

Fan Disch)

ZPTBF-D-2 (2B NIA

Pipe Tunnel Bstr

Fan Disch)

DENOT j CRITICAL

ii

STEPS ELEMENTS STANDARD SIU COMMENTS

REQUIRED

FOR UNSAT

6 Starting SIG Booster Operator starts all 4 SIG

Fans Booster Fans per initial

Select ON for desired conditions of JPM.

fan(s):

A SIG Booster Cue:

Fan

Pushbutton depressed,

red light is illuminated

B SIG Booster Cue:

Fan

Pushbutton depressed,

red light is illuminated

CSIG Booster Cue:

ii Fan Pushbutton depressed,

red light is illuminated

D SIG Booster Cue:

Fan

Pushbutton depressed,

red liaht is illuminated

~

Starting Pressurizer Operator selects A

Booster Fans PRESS BOOSTER Fan

to be started.

Position Press Booster

to desired fan:

FanA Cue:

Switch rotated

-

counterclockwise, red

light lit

FanB

STOP TIME

DENOTES CRITICAL

L

INITIAL CONDITIONS

A Unit 2 NC system heat-up is in progress following a short outage.

The Lower Containment Ventilation System had been shutdown during the outage.

All initial conditions have been satisfied for 0P/2/A/6450/0OlI Enclosure 4.2.

There are no outstanding R&Rs that will impact the performance of OP/2/A/6450/001,

Enclosure 4.2.

The SRO instructs the RO (YOU) to start the Unit 2 Lower Containment Ventilation System

per OP/2/A/6450/001, Enclosure 4.2. The SRO desires the following alignment:

Three (3) VL Fans(A, B, and C) in HIGH speed

One (1) Pipe Tunnel Booster Fan (A) in HIGH speed

All four (4) S/G Booster Fans (A, B, C, and D)ON

One (1) Pressurizer Booster Fan (A) ON

L

Enclosure 4.2 OP/2/N6450/001

Lower Containment Ventilation Operation Page 1 of 5

u

1. Limits and Precautions

1.1 All VL AHUs should be operated in the same speed

1.2 Only one Pipe Tunnel Booster Fan should be operated at a time.

1.3 three VL AHUs operating in "HIGH", "A", "B", and "C" should be in operation.

1.4 WHEN two VL AHUs operating, VL AHUs on opposite sides of Containment Building

should be in operation.

2. Initial Conditions

2.1 @ Unit 2 in Modes 1 - 5, cooling water is available to VL AHUs per OP/O/N6400/009

(Containment Ventilation Cooling Water System).

3. Procedure

0 3.1 Evaluate all outstanding R&Rs that may impact performance of this procedure.

3.2 Perform the following sections as applicable:

0 Section 3.3, Starting VL AHUs

0 Section 3.4, Starting Pipe Tunnel Booster Fan

0 Section 3.5, Starting S/G Booster Fans

0 Section 3.6, Starting Pressurizer Booster Fan

0 Section 3.7, Optimizing VL System Configuration During Normal Operation

0 Section 3.8, Stopping VL AHUs

0 Section 3.9, Stopping Pipe Tunnel Booster Fan

0 Section 3.10, Stopping SIG Booster Fans

0 Section 3.11, Stopping Pressurizer Booster Fan

3.3 Starting VL AHUs

3.3.1 Ensure in "AUTO":

- 2LCVU-D-1 (2A VL AHU Suction Damper Cntrl)

- 2LCVU-D-2 (2B VL AHU Suction Damper Cntrl)

__ 2LCVU-D-3 (2C VL AHU Suction Damper Cntrl)

__ 2LCVU-D-4 (2D VL AHU Suction Damper Cntrl)

Unit 2

Enclosure 4.2 OP/2/A/6450/001

Lower Containment Ventilation Operation Page 2 of 5

i/

NOTE: "LOW" speed light should be lit 7 seconds after starting VL AHU.

3.3.2 Select "LOW" for desired VL AHU(s):

__ 2A VL AHU Mode Select

__ 2B VL AHU Mode Select

__ 2C VL AHU Mode Select

__ 2D VL AHU Mode Select

3.3.3 Check "OPEN on operating VL AHU(s):

0 2LCVU-D-5 (2A VL AHU Disch Damper)

0 2LCVU-D-6 (2B VL AHU Disch Damper)

0 2LCVU-D-7 (2C VL AHU Disch Damper)

0 2LCVU-D-8 (2D VL AHU Disch Damper)

NOTE: VL AHU should be allowed to operate in "LOW" for 1 minute minimum prior to

selecting "HIGH".

-3.3.4 desired to operate in high speed, select "HIGH" for operating VL AHU(s):

'v

__ 2A VL AHU Mode Select

__ 2B VL AHU Mode Select

__ 2C VL AHU Mode Select

__ 2D VL AHU Mode Select

NOTE: Pipe Tunnel Booster Fans may be operated at different speed from VL AHUs.

3.4 - Starting Pipe Tunnel Booster Fan

3.4.1 Place one of the following in "HIGH":

__ 2A Pipe Tunnel Booster Fan

-OR

__ 2B Pipe Tunnel Booster Fan

3.4.2 neither fan is available for high speed operation, place one of the following

in "LOW":

__ 2A Pipe Tunnel Booster Fan

-

__ 2B Pipe Tunnel Booster Fan

Unit 2

Enclosure 4.2 OP/2/A/6450/001

Lower Containment Ventilation Operation Page 3 of 5

3.4.3 Check "OPEN" for operating fan:

0 2PTBF-D-1 (2A Pipe Tunnel Bstr Fan Disch)

0 STBF-D-2 (2B Pipe Tunnel Bstr Fan Disch)

3.5 Starting S/G Booster Fans

3.5.1 Select "ON" for desired fan(s):

__ A S/G Booster Fan

__ B S/G Booster Fan

__ C S/G Booster Fan

__ D S/G Booster Fan

3.6 Starting Pressurizer Booster Fans

3.6.1 Position "Press Booster" to desired fan:

-* FanA

-OR

__ FanB

3.7 Optimizing VL System Configuration During Normal Operation

NOTE: VL System may be operated in other than "optimized configuration" when conditions

warrant. Some examples of warranted conditions are as follows:

Minimizing Lower Containment temperature for personnel entry

Minimizing Lower Containment temperature during shutdown

Minimizing Lower Containment temperature to alleviate stress on equipment

.~ VL configuration to allow for equipment maintenance

A minimum of 2 VL AHUs should be in operation when 3 VR fans are operating to

ensure proper VR system flow.

0 3.7.1 Record Lower Containment Weighted Average Temperature (LCWAT) via

OAC point M2P0755. "F

-3.7.2 LCWAT indicates less than 115 OF, evaluate securing any operating RV

SRO pumps per 0P/0IA/6400/009 (Containment Ventilation Cooling Water

System).

Unit 2

Enclosure 4.2 OP/2/A/6450/001

Lower Containment Ventilation Operation Page 4 of 5

-3.7.3 LCWAT indicates less than 110 "F, perform one of the following:

__ 3.7.3.1 E four VL AHUs operating in "HIGH", stop one VL AHU per

Section 3.8.

__ 3.7.3.2 E three VL AHUs operating in "HIGH", place all VL AHUs in

"LOW" per Section 3.3.

___ 3.7.3.3 E four VL AHUs operating in "LOW", stop one VL AHU per

Section 3.8.

__ 3.7.3.4 three VL AHUs operating in "LOW", stop one VL AHU per

Section 3.8.

__ 3.7.4 LCWAT indicates 115 - 120°F, evaluate placing RV pumps in service per

OP/O/A/6400/009 (Containment Ventilation Cooling Water System).

__ 3.7.5 E LCWAT indicates greater than 120 "F, perform one of the following:

__ 3.7.5.1 four VL AHUs operating in "HIGH", place RV pumps in

service per OP/O/A/6400/009 (Containment Ventilation Cooling

Water System).

__ 3.7.5.2 three VL AHUs operating in "HIGH", place remaining

VL AHU in "HIGH" per Section 3.3.

__ 3.7.5.3 E four VL AHUs operating in "LOW", perform the following:

__ A. Stop one VL AHU per Section 3.8.

__ B. Place three VL AHUs in "HIGH" per Step 3.3.4.

__ 3.7.5.4 E three VL AHUs operating in "LOW", start remaining

VL AHU in "LOW" per Section 3.3.

__ 3.7.5.5 E two VL AHUs operating in "LOW", start third VL AHU in

"LOW" per Section 3.3.

3.8 Stopping VL AHUs

3.8.1 Select "OFF" for desired VL AHU(s):

__ 2A VL AHU Mode Select

__ 2B VL AHU Mode Select

__ 2C VL AHU Mode Select

__ 2D VL AHU Mode Select

Unit 2

Enclosure 4.2 OP/2/A/6450/001

Lower Containment Ventilation Operation Page 5 of 5

c 3.8.2 Check "CLOSED" for secured VL AHU(s):

0 2LCVU-D-5 (2A VL AHU Disch Damper)

0 2LCVU-D-6 (2B VL AHU Disch Damper)

0 2LCVU-D-7 (2C VL AHU Disch Damper)

0 2LCVU-D-8 (2D VL AHU Disch Damper)

3.9 Stopping Pipe Tunnel Booster Fan

3.9.1 Ensure in "OFF":

__ 2A Pipe Tunnel Booster Fan

__ 2B Pipe Tunnel Booster Fan

3.10 Stopping S/G Booster Fans

3.10.1 Place in "OFF":

__ S/G A Booster Fan

__ S/G B Booster Fan

__ S/G C Booster Fan

__ S/GDBoosterFan

3.1 1 Stopping Pressurizer Booster Fan

-3.11.1 Place "Press Booster" in "OFF".

End Of Enclosure

Unit 2

OP-MC-JPM-CP-AD:061T

PAGE^ OF 11

Prepared By

b a v i e w e d By

Approved By

TASK: Establish NC Pump Seal injection from the SSF

POSITION: NLO

Operator's Name

Location: Plant Method: Walkthrough

Estimated JPM Completion Time: 1 5Minutes

3ual JPM Completion Time: -Minutes

L

Required Time Critical Completion Time 8Minutes

Actual Time Critical Completion Time __ Minutes

The JPM Operator's performance was evaluated against the standards of this JPM and is determined

to be:

SATISFACTORYIUNSATISFACTORY (circle one)

Evaluator's Signature Date I I

References: EP/1/A/5000/ECA-0.0 Loss of All AC Power

JPM verified current with references by

Date I I

L..

Rev. 25/04-17-03

FOR TRAINING PURPOSES ONLY

OP-MC-JPM-CP-AD:OGIT

PAGE 2 OF 11

ii INITIAL CONDITIONS

A Loss of All AC has occurred on Unit 1. EP/l/A/5000/ECA-O.O (Loss of All AC Power) has been

implemented. The SRO has dispatched one (1) operator to 1ETA to swap 1EMXA4.

He then dispatches you to obtain the Green Folder at SSF and complete Enclosure 1 (Unit 1

SSF ECA-0.0 Actions)

This is a TIME CRITICAL JPM.

JPM OVERALL STANDARD: SSF Diesel in operation and supplying powerto ISLXG. ISLXG is

supplying power to SMXG and SMXG-1. Battery Chargers SDSP-1

and SDSP-2 supply breakers are closed. Standby makeup pump is

supplying NCP seal injection within 8 minutes.

L

NOTES: This JPM should be timed startinu from the OPS Kitchen. Once flow from the standby

makeup pumD is verified, the critical time stops.

The examiner shall provide a copy of EP/l/A/5000/ECA-O.O (Loss of All AC Power),

Enclosure 1 (SSF Actions) to allow proper place keeping, after the enclosure is

located at the SSF.

KA000068 G.06 4.1/4.3

ISK: MO-8308.1

d

FOR TRAINING PURPOSES ONLY

I

OP-MC-JPM-CP-AD:061T

PAGE 3 OF 11

b

START TIME

STEPS ELEMENTS STANDARD s/u COMMENT:

REQUIRED

FOR UNSAT

At SSF DIG Control Operator receives cue

Panel: and proceeds to RNO.

Check LINE Cue:

VOLTS -

APPROXIMATELY Meter reads 0Volts.

600V.

GO TO Step 1.c Same

Place the SSF Cue:

\ DIESEL

TEST/EMERG Switch rotated

switch to EMER clockwise

Check the SSF Cue:

DIESEL START

CONTROL switch Switch is in OFF

- OFF position

Place the SSF Cue:

DIESEL START

CONTROL switch Switch rotated

to ON clockwise

Check D/G starts Cue:

within 30 seconds

-

Background noise level

has increased, various

gage indications are up

I

0P-MC-JPM-CP-AD:OGlT

PAGE 4 OF 11

/

STEPS ELEMENTS STANDARD s/u COMMENT:

REQUIRED

FOR UNSAT

CONTINUED

Depress "TRIP" for Cue:

"NORMAL

INCOMING Pushbutton depressed,

BREAKER green lamp is

CONTROL" illuminated

At ISLXG: Operator proceeds to

Load Center ISLXG and

opens any breakers that

are closed. Repeat cue

as necessary.

Open all 600 V load &&: The BMXA feeder

breaker is normally open

center breakers:

and is m a critical step.

600V MCC BMXA

NORMAL INCOMING

FEEDER

600V MCC SMXG

600V MCC SMXG-1

MOTOR CONTROL

CENTER 1EMXH-1

ALTERNATE FEEDER

SSFSTDBYBATTERY

CHARGER SDSS

Cue (as applicable):

Switches rotated

counterclockwise or

trip pushbuttons

depressed, green

lamps are illuminated

DENOTES CRITICAL

I

0P-MC-JPM-CP-AD:OGIT

PAGE 5 OF 11

STEPS ELEME NTS STANDARD SIU COMMENT

REQUIRED

FOR UNSAT

-

At SMXG-1:

Open the following

breakers:

SMXG-1, FAE Same

(Battery Charger

No. SDSPI) Cue:

Breaker handle is

down

SMXG-1, RAD Same

(Battery Charger

No. SDSP2) Cue:

Breaker handle is

\ / down

4 4t ISLXG:

lepress "CLOSE" on Same

j00 V load center

xeaker 1SLXG-5B Cue:

Diesel Generator No. 5)

on breaker) Pushbutton depressed

and breaker indicates

closed

Jsing pistol grip

witches, close the

ollowing breakers

Close "ISLXGdC Same

CS" (SMXGI MCC

(Normal) Feed Cue:

Cntrl Switch).

Pistol grip rotated

lockwise, red light is

illuminated

-

DENOTES CRITICAL

I

OP-MC-JPM-CP-AD:OGlT

PAGE6OF11

'\

STEPS ELEMENTS STANDARD

REQUIRED

FOR UNSAT

4 ONTINUED

Wait 10 Seconds he:

I O seconds have

?lapsed

Same

Close "1SLXG-4C

CS" (SMXG MCC

:ue:

(Normal) Feeder

Cntrl Switch).

Pistol grip rotated

clockwise, red light is

illuminated

5 i t SSF Control Panel:

)pen the following

ralves:

1NV-842AC Same

(Standby MIU

Pump Suction Isol) Cue:

Pushbutton depressed,

red light is illuminated

1NV-849AC Same

(Standby M/U

pump Cont Outside Cue:

Isol)

Pushbutton depressed

red light is illuminated

DEN0 j CRITICAL

I

OP-MC-JPM-CP-AD:OGlT

PAGE 7 OF 11

STEPS ELEMENTS STANDARD SIU COMMENT

REQUIRED

FOR UNSAT

5 CONTINUED

Check the following

valves - OPEN

INV-1013C Same

(Standby MIU

Pump to NC Pump Cue:

Seals Isol)

Red light is illuminated

1NV-842AC Same

(Standby MIU

Pump Suction Isol) Cue:

Red light is illuminated

1NV-849AC Same

(Standby MIU

Pump Cont Outside Cue:

Isol)

Red light is illuminated

Start Unit 1 Standby Same

Makeup Pump

Cue:

Pushbutton depressed,

red light is illuminated

Check Unit 1 Same

Standby Makeup

Pump flow - Cue:

(1NVP6420)

GREATER THAN Meter indicates 28 GPM

OR EQUAL TO 26

-

GPM Stop Time for Time

Zritical Task

DENOTI CRITICAL

I

OP-MC-JPM-CP-AD:061T

PAGE 8 OF 11

-

STEPS ELEMENTS STANDARD s/u COMMENT:

REQUIRED

FOR UNSAT

5 CONTINUED

Check INV-1012C Same

(Standby M/U

Pump to Cont Cue:

Sump) - CLOSED

Green lamp is

illuminated

Check SSF D/G - Same

RUNNING

Cue:

SSF DIG is fiJNNI1.S

Check SSF D/G Same

FREQUENCY -

AT 60 Hz Cue:

Meter indicates 60 Hz

Check SSF DIG Same

VOLTAGE - AT

600V. Cue:

Meter indicates 600

volts

u

DENOTES CRITICAL

OP-MC-JPM-CP-AD:061T

-

/

PAGE 9 OF 11

STEF

I

ELEMENTS STANDARD s/u COMMEN7

- -

REQUIRED

FOR UNSAT

6 At SMXG-1:

Close SMXG-1, Same

FAE (BATTERY

CHARGER NO. Cue:

SDSPI)

Breaker handle pulled

into the UP position

Wait 10 Seconds Same

Cue:

I O seconds have

?lapsed

Close SMXG-1, jame

RAD (BATTERY

CHARGER NO. he:

SDSP2)

breaker handle pulled

ito the UP position

Wait 10 Seconds ame

ue:

I seconds have

apsed

DENOTES CRITICAL

I

OP-MC-JPM-CP-AD:OGIT

PAGE 10 OF 11

STEP: ELEMENTS STANDARD COMMENT:

REQUIRED

FOR UNSAT

7 At ISLXG:

Using pistol grip Same

switch, close

1SLXGdD CS Cue:

(SDSS Battery

Charger Cntrl Pistol grip rotated

Switch), clockwise, red light is

illuminated

Wait 10 Seconds 10secondshave

elapsed

8 4t SMXG: Same

insure SMXG-F5A (Unit Cue:

I Pzr Heater Group #28,

, 155, #56 Fdr) is closed.

Breaker is closed

i t SSF Control Panel:

9 Note:Examiner should

point to these values on

sach respective meter

Check SSF DIG Same

FREQUENCY - Cue:

AT 60 Hz

Meter indicates 60 Hz

Check SSF DIG Same

VOLTAGE -AT he:

600V.

Meter indicates 600

rolts

Check SSF same

Generator Load -

he:

LESS THAN OR

EQUAL TO 700 KW deter indicates 500 KW

-

Unit 1 SSF ECA-0.0 Actions Rev. 15

1. (Continued)

- f. Check DIG starts within 30 seconds. f. Perform the following:,

- 1) Place the "SSF DIESEL START

CONTROL" switch to "OFF.

- 2) E 2 D/G start attempts have been

performed, THEN observe Notes

prior to Step 11 and GO TO Step 11.

- 3) Wait 20 seconds and RETURN T O

Step 1.e.

- g. Depress "TRIP for "NORMAL

INCOMING BREAKER CONTROL"

2. At ISLXG:

- a. Open all 600 V load center breakers.

3. AtSMXGl:

a. Open the following breakers:

- SMXGl - FAE (SDSPl Battery

Charger)

- SMXGl - RAD (SDSP2 Battery

Charger).

.- ,- ~

MNS /LOSS OF ALL AC POWER I PAGE NO.

EP/1/N5000/ECA-O.O Enclosure 1 - Page 3 of 7 33 Of I27

UNIT 1 -

Unit 1 SSF ECA-0.0 Actions

Rev. 15

L,

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

Yellow "TIME CRITICAL" tags are located next to switches used in Steps 4

through 5.c.

4. At 1SLXG:

- a. Depress "CLOSE on 600 V load center

breaker ISLXGdB (SSF D/G)(on

breaker). I

b. Using pistol grip switches, close the

following breakers:

- 1) Close "ISLXGdC CS" (SMXGI

MCC (Normal) Feeder Cntrl Switch).

- 2) Wait 10 seconds.

- 3) Close "ISLXG-4C CS" (SMXG MCC

(Normal) Feeder Cntrl Switch).

5. At SSF Control Panel:

a. Open the following valves: a. Perform the following:

- 1NV-842AC (Standby MIU Pump - 1) Call Control Room or operator in

Suction Isol) 1ETA room to ensure 1EMXA4 has

been swapped to alternate power.

- 1NV-849AC (Standby MIU Pump

Cont Outside Isol).

NOTE Indicating lights on

1NV-842AC and

1NV-849ACswitches

will light when

1EMXA4 is swapped.

- 2) WHEN 1EMXA4 is swapped, THEN

open valves.

- 3) Do not continue until 1EMXA4 is

swapped to alternate power.

/ LOSS OF ALL AC POWER I PAGE NO.

Enclosure 1 - Page 4 of 7 34 of 127

-

Unit 1 SSF ECA-0.0 Actions Rev. 15

A C T I O N ~ X P E C T E D RESPONSE R E S P O N S E NOT O B T A I N E D

- c. Start Unit 1 Standby Makeup Pump.

- d. Check Unit 1 Standby Makeup Pump - d. Ensure valves in Step 5.b are properly

flow (lNVP6420) - GREATER aligned.

THAN OR EQUAL TO 26 GPM.

NOTE Remaining steps in this enclosure are not time critical, but must be completed

in a timely manner.

- e. Check lNV-IO12C (Standby M/U Pump e. Perform the following:

Disch to Cont Sump) - CLOSED.

- 1) Stop Unit 1 Standby Makeup Pump.

- 2) Close 1NV-1012C (Standby M/U

Pump Disch to Cont Sump).

- 3) Do not continue until 1NV-1012C is

closed.

- 4) RETURN Step 5.c.

1I

I

EP/1/N500O/ECA-O.&p& ($y/ f LOSS OF ALL AC POWER I PAGE NO.

8 35 of 127

\ 3 \ 9 c e & A Enclosure 1 - Page 5 of 7

UNIT 1 I -

Unit 1 SSF ECA-0.0 Actions Rev. 15

ACT ION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

5. (CoQtinued)

- f. Check SSF. D/G - RUNNING. f. Perform the following:,

- I) Ensure SMXG-F5A (Unit 1

Pressurizer Heaters 28/55/56

Feeder) is closed.

2) Notify OSM of the following:

- IF AT ANY TIME Unit 1 offsite

power is lost to ISLXG (powered

from 6900 V switchgear ITC),

THEN Enclosure 1 (Unit 1 SSF

- ECA-0.0 Actions) must be

performed again.

- 3) RETURN To step in effect in body

of this procedire.

- g. Check SSF D/G "FREQUENCY" - AT - g. Adjust the "SSF DIESEL GOVERNOR

/ 60 Hz. CONTROL" to obtain 60 Hz.

- h. Check SSF DIG "VOLTAGE" - A T - h. Adjust "SSF DIESEL VOLTAGE

600V. CONTROL" to obtain 600V.

6. At SMXGI:

- a. Close SMXGI - FAE (SDSPI

BATTERY CHARGER).

- b. Wait 10 seconds.

- c. Close SMXGI - RAD (SDSP2

BATTERY CHARGER).

- d. Wait 10 seconds.

7. AtlSLXG:

- a. Using pistol grip switch, close

"1SLXG-5D CS" (SDSS Battery

Charger Cntrl Switch).

,

' LOSS OF ALL AC POWER I

PAGE NO.

Enclosure 1 - Page 6 of 7 36 of 127

UNIT1 -

Unit 1 SSF ECA-0.0 Actions

Rev. 15

ACTIONlEXPECTED RESPONSE RESPONSE NOT OBTAINED

9. At SSF Control Panel:

- a. Check SSF D/G "FREQUENCY" - AT - a. Adjust the "SSF DIESEL GOVERNOR

60 Hz. CONTROL" to obtain 60 Hz.

- b. Check SSF DIG "VOLTAGE" - A T - b. Adjust "SSF DIESEL VOLTAGE

600V. CONTROL" to obtain 600V.

- c. Check SSF Generator Load - LESS - c. Contact station management to

THAN OR EQUAL TO 700 KW. evaluate reducing load.

Ensure SSF DIG room intake louvers are

open (located above rollup door in D/G

room).

F * -

MNS . qYy'Loss OF ALL Ac POWER I PAGE NO.

EP/~/AEXWO/ECA-OJJ %e 9%'"

GbY;%p\ % os -

Enc~osure1 page7 of 7 37 of 127

Rev. 15

UNIT 1 W" / -

Unit 1 SSF ECA-0.0 Actions

c Y

A C T I O N l E X P E C T E D RESPONSE

1 RESPONSE NOT O B T A I N E D

NOTE lnabilityto start DIG or a D/G trip without apparent cause may indicate an

electrical failure of the Fuel Oil Solenoid valve.

Opening the "FUEL OIL SOLENOID BYPASS" valve bypasses all trips

(including manual).

11. IF A T ANY TIME SSF D/G trips without

apparent cause, OR is unable to be

started without apparent cause, THEN:

- a. Ensure "GENERATOR BREAKER

CONTROL" indicates "OPEN".

- b. Ensure the "SSF DIESEL START

CONTROL" switch is in "OFF".

- c. Turn the manual knob on the "FUEL

OIL SOLENOID BYPASS" (located on

the SSF control room side of D/G, 3 R

from floor) fully clockwise.

- d. RETURN To Step 1 .e.

MC-OPJPM-CNT-VX:204

PAGE 1 OF 9

Prepared By:

b>viewed

" By:

Approved By:

TASK: Start the 2A Hydrogen Analyzer

POSITION: NLO

Operator's Name

Location: Plant Method: Walkthrough

Estimated JPM Completion Time: 20 Minutes

Actual JPM Completion Time: __ Minutes

-he JPM Operator's performance was evaluated against the standards of this JPM and is determined

to be:

SATlSFACTORY/UNSATISFACTORY (circle one)

Evaluator's Signature Date / /

References: EP/2/AJ5000/FR-1.3 Response to Voids in Reactor Vessel

E Pl2/Al5000lG-1 Generic Enclosures

JPM verified current with references by

Date I I

Rev. 00104-08-03

FOR TRAINING PURPOSES ONLY

MC-OPJPM-CNT-VX204

PAGE 2 OF 9

i/

INITIAL CONDITIONS

You a r e the Unit 2 Auxiliary Building Rounds person.

A Steam Generator Tube Rupture h a s occurred on Unit 2. T h e procedure currently in use is

EP/2/A/5000/FR-1,3, Response to Void in Reactor Vessel. It is complete to S t e p 15.b and now directs

starting the Hydrogen Analyzers.

The C/R SRO dispatches you to place the 2A Hydrogen Analyzer in service per

EP/2/A/5000/G-l Enclosure 5 (Placing the Hydrogen Analyzers in Service).

Safety Injection and the Diesel Generator Load Sequencers have been reset.

JPM OVERALL STANDARD: " 2 A Hydrogen Analyzer in service.

VOTES: T h e evaluator may desire to check out key # 172 prior to beginning

this JPM to reduce examination length. If so, provide the key on

u s t e p #2 a n d cue accordingly.

Ensure any keys used in the performance of this JPM are

returned to WCC prior to leaving the site.

KA 028 ~ 4 . 0 33 . ~ 3 . 3

TASK: MO-8004

MC-OPJPM-CNT-VX:204

PAGE 3 OF 9

i/

START TIME

~

STANDARD SIU COMMENT

REQUIRED

~

- FOR UNSAT

1 Ensure the following: Operator verifies from

initial conditions of JPM

SI reset that these items have

been reset

DIG Load

Sequencers reset

2 Obtain one key 172 and

two keys 178 from the Note to evaluator:

Control Room black box

of keys. After receiving the cue

below, the operator

proceeds to the Work

Control Center and

checks out key # 172.

Use of key # 178 will be

simulated during this

JPM.

Cue:

Key # 172 is missing

from the Control Room

black box. Obtain key

172 using an alternate

method.

Cue:

Simulate the use of key

178.

+DENOTES CRITICAL

MC-OP-JPM-CNT-VX204

PAGE 4 OF 9

-

STEPS ELEMENTS STANDARD SIU COMMENTS

REQUIRED

FOR UNSAT

Close 2EMXA-R7D (H2 Same

Analyzer and PAMS

Panel Heat Trace) (aux

bldg, 750, FF-57) Cue:

Breaker rotated

clockwise

Start 2A H2 Analyzer as Same

follows:

Proceed to 2MMIMT

6850 H2 ANALYZER

TRAIN A PANEL (750

elevation in cable

sDreadina room)

5 Use key 172 to access Same

remote panel

Inside remote panel, use Note to evaluator:

key 178 to place

ISOLATION VALVES Use of key #178 will be

OPEN switch to O N simulated.

Cue:

Key inserted, switch

rotated clockwise

Check POWER ON light Same

above ISOLATION

VALVES OPEN switch- Cue:

LIT

Light is illuminated

Place HYDROGEN Same

ANALYZER SAMPLE

ENABLE SWITCH to Cue:

SAMPLE.

Switch rotated

clockwise

DENOTl i CRITICAL

MC-OP-JPM-CNT-VX:204

PAGE 5 OF 9

STEPS ELEMENTS STANDARD SIU COMMENT!

REQUIRED

FOR UNSAT

-

9 Select sample location as

follows:

x

Place Same

HYDROGEN

ANALYZER Cue:

SAMPLE

SELECT switch to Switch rotated

UPPER CONT counterclockwise

Check POWER Same

ON light for

selected location - Cue:

OFF

Light is off

IF AT ANY TIME Same

station

management Cue:

desires sample

from alternate Station management

location, THEN does not desire to

place sample another

HYDROGEN location

ANALYZER

SAMPLE

SELECT switch to

desired location:

OPER LEVEL

SIG CAVITY

MC-OP-JPM-CNT-VX204

PAGE 6 OF 9

i

STEPS ELEMENTS STANDARD COMMENT.

REQUIRED

- *I 0 Depress OFF Same

FOR UNSAT

pushbutton on SAMPLE

ROUTED TO PAMS Cue:

PANEL switch

Switch is depressed

11 Place OFF-STANDBY- Same

ANALYZE switch to

ANALYZE Cue:

Switch rotated

clockwise

12 Depress Same

LOCAUREMOTE

SELECTOR pushbutton Cue:

Pushbutton depressed

I 3 Ensure H2DUAL Same

RANGE S W is in 0.30%

range Cue:

\

I

Switch is in the

0 5 0 % range position

-

4 Place FUNCTION Same

SELECTOR to

SAMPLE Cue:

Switch rotated

counterclockwise

-rl i CRITICAL

MC-OP-JPM-CNT-VX:204

PAGE 7 OF 9

ELEMENTS STANDARD COMMENT:

STEPS

REQUIRED

FOR UNSAT

IOnot continue until 5 he:

15

iinutes have elapsed

rive minutes have

!lapsed.

16 E a "COMMON ALARM" he:

lit, THEN perform the

ollowing: The COMMON ALARM

ight is LIT.

Depress "ALARM 3perator resets the

RESET" 4arm.

-

IF"COMM0N Cue:

ALARM clears,

THEN GO TO The COMMON ALARM

Step 4.n. light is DARK.

Operator proceeds to

Step 4.n.

Notify control room that Cue:

2A H2 Analyzer is in

service Control room SRO

acknowledges your

communication.

STOP TIME

<*,DENOTES CRITICAL

INITIAL CONDITIONS

You are the Unit 2 Auxiliary Building Rounds person.

A Steam Generator Tube Rupture has occurred on Unit 2. The procedure currently in

use is EP/2/A/5000/FR-1.3, Response to Void in Reactor Vessel. It is complete to Step

15.b and now directs starting the Hydrogen Analyzers.

The CIR SRO dispatches you to place the 2A Hydrogen Analyzer in service per

EP/2/A/5000/G-l Enclosure 5 (Placing the Hydrogen Analyzers in Service).

Safety Injection and the Diesel Generator Load Sequencers have been reset.

c

MNS GENERIC ENCLOSURES PAGE NO.

EP/2/A/5000/G-I 15 of 99

Enclosure 5 - Page 1 of 4

Rev. 18

UNIT 2 Placing H2 Analyzers In Service

1. Ensure the following:

- a. S/I reset.

- b. D/G Load sequencers reset.

- 2. Obtain one key 172 and two keys 178 from Control Room black box of keys.

- 3. Close 2EMXA, R7D (H2 Analyzer and PAMS Panel Heat Trace) (aux bldg, 750, FF-57).

4. Start 2A HZ Analyzer as follows:

- a. Proceed to "2MMIMT 6850 H2 ANALYZER TR A panel (750' elevation in cable spreading

room).

- b. Use key 172 to access remote panel.

\ - c. Inside remote panel, use key 178 to place "ISOLATION VALVES OPEN" switch to "ON".

- d. Check "POWER ON" light above "ISOLATION VALVES OPEN" switch - LIT.

- e. Place "HYDROGEN ANALYZER SAMPLE ENABLE switch to "SAMPLE".

f. Select sample location as follows:

- 1) Place "HYDROGEN ANALYZER SAMPLE SELECT" switch to "UPPER CONT".

- 2) Check "POWER ON" light for selected location - OFF.

3) IF AT ANY TIME station management desires sample from alternate location, T m p l a c e

"HYDROGEN ANALYZER SAMPLE SELECT' switch to desired location:

- "OPER LEVEL"

- "S/G CAVITY".

- g. Depress "OFF" pushbutton on "SAMPLE ROUTED TO PAMS PANEL" switch.

- h. Place "OFF/STANDBY/ANALYZE switch to "ANALYZE'.

- i. Depress "LOCAUREMOTE SELECTOR" pushbutton.

T - j. Ensure "H2 DUAL RANGE S W in 0-30% range.

MNS GENERIC ENCLOSURES PAGE NO.

EP/2/AJ5000/G-1 16 Of 99

Enclosure 5 - Page 2 of 4 Rev. 18

UNIT 2 Placing Hz Analyzers In Service

4. (Continued)

- k. Place "FUNCTION SELECTOR" to "SAMPLE".

- I. Do not continue until 5 minutes have elapsed.

m. E "COMMONALARM" lit, THEN perform the following:

-

NOTE A low gas flow condition may be causing the "COMMONALARM" and

may clear itself once condensation is removed from the sample line.

- 1) Depress "ALARM RESET".

- 2) E "COMMONALARM" clears, THEN GO TO Step 4.n.

3) "COMMON ALARM will not clear, THEN perform the following:

- a) Notify IAE to investigate alarm.

- b) Notify control room to disregard 2A H2 Analyzer reading until IAE clears alarm.

- c) S m S t e p 5.

- n. Notify control room that 2A HZ Analyzer is in service.

5. Start 26 H2 Analyzer as follows:

- a. Proceed to "2MMIMT 6860 H2 ANALYZER TRAIN B" panel (733' elevation in vital battery

area).

- b. Use key 172 to access remote panel.

- c. Inside remote panel, use key 178 to place "ISOLATION VALVES OPEN" switch to "ON".

- d. Check "POWER ON" light above "ISOLATION VALVES OPEN" switch - LIT.

- e. Place "HYDROGEN ANALYZER SAMPLE ENABLE" switch to "SAMPLE".

II I I 11

ll I

MNS GENERIC ENCLOSURES PAGE NO.

EP/2/AJ5000/G-1 17 of 99

Enclosure 5 - Page 3 of 4 Rev. 18

UNIT 2 Placing Hz Analyzers In Service

5. (Continued)

f. Select sample location as follows:

- 1) Place "HYDROGEN ANALYZER SAMPLE SELECT" switch to "UPPER CONT".

- 2) Check "POWER ON" light for selected location - OFF.

3) IF AT ANY TIME station management desires sample from alternate location, T m p l a c e

"HYDROGEN ANALYZER SAMPLE SELECT" switch to desired location:

- 0 "OPER LEVEL"