ML022690438

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August 2002 Exam 50-400/2002-301 Draft JPMs & Outlines
ML022690438
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 03/22/2002
From: Ernstes M
Division of Reactor Safety II
To: Scarola J
Carolina Power & Light Co
References
50-400/02301 50-400/02301
Download: ML022690438 (224)


See also: IR 05000400/2002301

Text

Draft Submittal

(Pink Paper)

c-4. Administrative Questions/JPMs

ý2. ,In-plant JPMs

x3. Control Room JPMs (simulator JPMs)

'-4. Administrative Topics Outline ES-301-1

Control Room Systems and Facility Walk-Through

Test Outline ES-301-2

SHEARON HARRIS

EXAM 2002-301

50-400

AUGUST 26 - 29, 2002

ES-301 Administrative Topics Outline FORM ES-301-1

Facility: HARRIS Date of Examination: 26-Aug-02

Examination Level: RO Operating Test Number:

Describe method of evaluation:

Administrative 1. ONE Administrative JPM, OR

Topic/Subject 2. TWO Administrative Questions

Description

(KA #)

A.1 Determine Rod Misalignment Using Thermocouples (AOP-001)

CONDUCT OF

OPERATIONS

(2.1.19)

Perform a Manual Power Range Heat Balance Calculation

(OST-1204)

(2.1.25)

k.2 Review an Equipment Clearance (OPS-NGGC-1301)

EQUIPMENT

CONTROL

(2.2.13)

N.3 Perform Licensed Operator Actions to Establish a Liquid Waste

RADIATION' Release

CONTROL

(2.3.11)

A.4 Activate the Emergency Response Organization - Dialogic

EMERGENCY System (PEP-310)

PLAN

(2.4.43)

NUREG-1021, Revision 8, Supplement I

ES-301 Administrative Topics Outline FORM ES-301-1

Facility: HARRIS Date of Examination: 26-Aug-02

Examination Level: SRO Operating Test Number:

Describe method of evaluation:

Administrative 1. ONE Administrative JPM, OR

Topic/Subject 2. TWO Administrative Questions

Description

(KA #)

A.1 CODCO Change the Dedicated SPDS Screen Location (OP-163)

OPERATIONS

(2.1.19)

Perform a Manual Power Range Heat Balance Calculation

(OST-1204)

(2.1.25)

4.2 Review an Equipment Clearance (OPS-NGGC-1301)

EQUIPMENT

CONTROL

(2.2.13)

Question Topic - License Requirements for Conducting a Waste

k.3 Release with Inoperable Instrumentation and Administrative

RADIATION Controls Ensuring Requirements Met (2.3.6)

CONTROL Question Topic - Selection Process for Individuals Performing

Emergency Entries into Radiation Fields Resulting in Exceeding

Permissible Exposure Limits (2.3.4)

A.4 Determine Protective Action Recommendations (PEP-1 10)

EMERGENCY

PLAN

(2.4.44)

NUREG-1021, Revision 8, Supplement 1

FORM ES-301-2

ES-301 Control Room Systems and Facility Walk-Through Test Outline

HARRIS Date of Examination: 26-Aug-02

Facility:

Examination Level: RO Operating Test Number:_

B.1 Control Room Systems

Type Safety

System/JPM Title Code* Function

(KA #)

DAS 3

a.Perform Control Rod Exercise Test (003AA1.05)

b. LOOP While Paralleling EDG NAS 6

from MCB for Testing (OP-1 55) (064A4.01)

MS 8

C.Decreasing CCW Surge Tank Level (AOP-014) (008A2.02)

DASL 5

d.Manually Align Containment Spray (PATH-l) (026A4.01)

DASL 2

(006A4.05)

MSL 4P

f. Hi h RCS Pre ssure W hl So d(A P 0 ) (005A2.02)

acr

NSL 7

e.

Transfer Ai

H~tL nChgR torincru u ati o ss0 ofP

1)( OP0 7

I (015A4.02)

(015A4.02)

DL 1

Hig RSta r essuaHyroenWhieSombide (AOP-125) (003AA1.02)

DRL 2

(065AA1.02)

DL 5

(028A4.01)

Room, (S)imulator,

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol

(L)ow-Power, (R)CA

NUREG-1021, Revision 8, Supplement 1

K-,

FORM ES-301-2

ES-301 Control Room Systems and Facility Walk-Through Test Outline

Date of Examination: 26-Aug-02

Facility: HARRIS

SRO-U Operating Test Number:

Examination Level:

B.1 Control Room Systems

Safety

Function

System/JPM Title Type

Code* (KA #)

DAS 3

a.

Exercise Test (003MA1.05)

Perform Control Rod

Testing (OP-155) NAS 6

b.

Paralleling EDG from MCB for (064A4.01)

LOOP While

C.

rd.

e.:

f.

B.2 Facility Walk-Through

(AOP-001) DL1

a.

Dropped Rod Recovery

Local Actions for a (003AA1.02)

Aent 2

DRL

rmbn,(~w (065AA1.02)

ak Moiid

'a ietfo

  • Tp odes

5

(O-15 DIL

y Reobnr (028A4.01)

UaHyrogen

Start

path, (C)ontrol Room, (S)imulator,

11I

(L)ow-Power, (R)CA

NUREG-1021, Revision 8, Supplement 1

ES-301 Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2

Facility: HARRIS Date of Examination: 26-Aug-02

Examination Level: SRO-l Operating Test Number:

B.l Control Room Systems Type Safety

Safety

System/JPM Title eFunction

Code t (KA #)

a. DAS 6

Perform Control Rod Exercise Test (003AA1.05)

b.NA6

LOOP While Paralleling EDG from MCB for Testing (OP-155) NAS 6

C.

MS 8

Decreasing CCW Surge Tank Level (AOP-014) (008A2.02)

d. DASL 5

Manually Align Containment Spray (PATH-1) (026A4.01)

e. DASL 2

Transfer to Hot Leg Recirculation (EPP-011) (006A4.05)

f" DSL 4P

Start an RCP Following Maintenance (OP-100) (003A4.06)

g" NS 7

Power Range NI Gain Adjustment (OP-105) (015A4.02)

B.2 Facility Walk-Through

a. DL 1

Local Actions for a Dropped Rod Recovery (AOP-001) (O3AA1.02)

b.DRL 2

(065AA1.02)

Manually Align Charging Due to a Loss of IA(AOP-017)

C. c.DL 5

(028A4.01)

Start Up a Hydrogen Recombiner (OP-125)

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator,

(L)ow-Power, (R)CA

NUREG-1021, Revision 8, Supplement 1

JPM SRO-A.I-I

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM SRO-A. 1.1

Perform Review of Daily Surveillance Requirements

Log

CANDIDATE:

EXAMINER:

5)$* 1 r

Page I of 6

JPM SRO-A. l-I

HARRIS

REGION II

3/4>

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Perform Review of Daily Surveillance Requirements Log

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

KA: 2.1.18 IMPORTANCE: SRO 3.0 RO NA

KA STATEMENT: Ability to make accurate, clear and concise logs, regards,

status boards, and reports.

TASK STANDARD: Four of five (4/5) errors on attached log sheet are identified.

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PERFORM SIMULATE

PREFERRED EVALUATION METHOD:

REFERENCES: OST-1021, Daily Surveillance Requirements, Daily Interval, Mode

1 and 2

VALIDATION TIME: 15 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 6

JPM SRO-A.1-I

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

"* Complete OST-1021, Attachment 4, for the 0300 readings using values expected at

100% power.

"* Substitute the following incorrect data:

"* Accumulator CLAB Previous Day Level @ 68% (both 924 and 926) with 0300

readings at 78% and 79%, while indicating sampling is NOT required.

"* RWST Level Channel 993 @ 91%.

"* Pressurizer Pressure channels 455 @ 2210 psig, 456 @ 1960 psig, 457 @ 2230

psig while indicating acceptance criteria is met.

0

"* Containment Temperature channel TCV97540 as "NA", 7542 @ 121 F, 7541 @

I 16'F while indicating acceptance criteria is met.

"* EDG Room Temperature channel TDG6903A @ @ I I8F and TDG6903B @

121°F

OST-1021, "Daily Surveillance Requirements, Daily Interval, Mode 1 and 2,"

Attachment 4, "Daily Surveillance Requirements Log"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

room steps shall be performed for this JPM, including any required communications. I

will provide initiating cues and reports on other actions when directed or asked by

you. Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

The Daily Surveillance Logs for 0300 have been completed.

INITIATING CUE(S):

You are to review the logs, noting all errors.

Page 3 of 6

JPM SRO-A.1-1

HARRIS

START TIME:

  • DENOTES CRITICAL STEP

STAN DARD NOTES SAT/

JPM PROC ELEMENT

UNSAT

STEP STEP

NA Obtains logs Obtains logs from

examiner

CUE: PROVIDE COMPLETED SET OF 0300 NOTE: Only

those items in the

LOGS TO CANDIDATE. logs which are

incorrect are

identified.

  • 2 A.ttach 4 Cold Leg Accumulator Identifies that level has Critical to

increased more than identify error that

Sheet 1 CLA B requires sampling sampling is

9% and requires

due to increase in level of> required.

9% sampling

that level is

  • 3 Attach 4 RWST Level Channel 993 is Identifies Critical to

identify that level

below minimum required below minimum

Sheet 2 is below

level of 92% required

minimum

required.

Determines average Critical to

  • 4 Attach 4 Pressurizer Pressure does

pressure is acceptable, identify that with

Sheet 3 not meet acceptance criteria only two

due to pressure on one of but acceptance criteria

not met due to one of channels

the only two operable operable, both are

channels (PT-455) being < the only two operable

channels being < 2220 required to be

2220 psig > 2220 psig.

psig

4 Identifies that Critical to

  • 5 Attach Containment Temperature identify that

Sheet 8 temperature exceeds

Channel TI-7542 exceeds temperature is

limit of 120'F maximum limit

above maximum

allowed.

Attach 4 Identifies that Critical to

  • 6 Diesel Generator Room 261 identify that

temperature TDG6903B temperature exceeds

Sheet 10 temperature is

exceeds limit of 120'F maximum limit

above maximum

allowed.

TASK COMPLETE

STOP TIME:

Page 4 of 6

JPM SRO-A. 1

HARRIS

Include copy of COMPLETED OST-1021 LOG

SHEETS here, ensuring errors are included as directed

in setup instructions.

Page 5 of 6

Attachment 4

Sheet 3 of 15

Daily Surveillance Reanuirements Too

TECH SPEC 4.2.5.1: 4.3.1.1.9. 10: 4.3,2.1.1d, Sa3, 3c3, Sc, 56

PARAMETER PRESSURIZER PRESSURE

INSTRUMENT PRC0457 PRC0456 PRC0455 CALCULATION INDEPENDENT ACCEPTANCE

(MCB OR ERFIS) PI-457 PI-456 P1-455 COMPLETED VERIFICATION E N/A

~~~COMPLETED CIEI

h I

ACCEPTANCE CHANNEL

CRITERIA CHECK

MODE

0300 z2-350 /44,0 Z72/

1500

2100

INSTRUCTIONS

NOTE: Calculations must be done with either the MCB Indicators OR ERFIS

indications, NOT a combination.

If all operable channels are greater than or equal to the

acceptance criteria, calculations are not required.

rThT.r$T<T'rCMC rr'n tnt'OCTflt7'fl 5P'CCT1PW

'<4

0300: 0 Z* + __O-- + 2710 = 4'et e- ÷(# Operable

PRC0457 PRC0456 PRC0455 Channels u:sed PRESSURIZER

PI-457 PI-456 PI-455 Normally 3 PRESSURE

0900: + + +(* Operable

PRCO457 PRC0456 PRC0455 Channels uised PRESSURIZER

PI-457 PI-456 PI-455 Normally 3 PRESSURE

1500: - + + _ __(# Operable

PRC0457 PRC0456 PRC0455 Channels used PRESSURIZER

PI-457 PI-456 PI-455 Normally 3) PRESSURE

2100: + + = (# Operable

PRC0457 PRC0456 PRC0455 Channels used PRESSURIZER

PI-457 PI-456 PI-455 Normally 3) PRESSURE

ACCEPTANCE CRITERIA FOR PRESSURIZER PRESSURE (must meet one of the following):

Average of operable MCB indicator channels greater than or equal to

2205 psig.

Q Average of operable ERFIS points greater than or equal to 2202 psig.

t If three MCB indicators are not available, then the lowest channel

should be greater than or equal to 2220 psig.

4.V, If three ERFIS points are not available, then the lowest channel should

be greater than or equal to 2211 psig.

OST-1021 Rev. 44 Page 16 of 36

Attachment 4

Sheet 3 of 15

Dailv Surveillance Re2uirements Loa

TECH SPEC 4.2.5.;:4.3.1.1.9, 10; 4.32.1.Id, 3aS, 3c3, 5c, 6d

PARAMETER PRESSURIZER PRESSURE

INSTRUMENT PRC0457 PRC0456 PRC045S CALCULATION INDEPENENT ACCEPTANCE

(MOO OR ERFIS) PI-457 PI-456 PI-45! COMPLETED VERIFICATION CRCTERIA MET N/A

COMPLETED

ACCEPTANCE

ACCETAC SEE BELOW N/A N/A N/A CHANNEL

CHEL

CRITERIA CHECK

MODE 1 - 1.2,3

09Z

1500

2100

INSTRUCTIONS

NOTE: " Calculations must be done with either the MCB Indicators OR ERFIS

indications, NOT a combination.

If all operable channels are greater than or equal to the

acceptance criteria, calculations are not required.

CALCULATIONS FOR PRESSURIZER PRESSURE

di

0300: ZZ30 + AIA + Z2/o - ___r._ ÷(# Operable SZIz ER

PRC0457 PRC 0-4 56 PRC0455 Channels used PRESSURIZER

PI-457 PI-456 PI-455 Normally 3) PRESSURE

0900: + = +-(# Operable

PRC0451 PRC0456 PRC0455 Channels used PRESSURE

PI-457 PI-456 PI-455 Normally 3) PRESSURIZER

1500: - + + = __(# Operable

PRC0457 PRC0456 PRC0455 Channels used PRESSURE

PI-457 PI-456 PI-455 Normally 3) PRESSURE

2100: _ _ _ + _ _ + _ _ ,_(# Operable PRESSURE

PRC0457 PRC0456 PRC0455 Channels used PRESSURIZER

PI-457 PI-456 PI-455 Normally 3)

ACCEPTANCE CRITERIA FOR PRESSURIZER PRESSURE (must meet one of the following):

1. Average of operable MCB indicator channels greater than or equal to

2205 psig.

2. Average of operable ERFIS points greater than or equal to 2202 psig.

( If three MCD indicators are not available, then the lowest channel

should be greater than or equal to 2220 psig.

4. if three ERFIS points are not available, then the lowest channel should

be greater than or equal to 2211 psig.

OST-1021 Rev. 44 Page 16 of 36

Attachment

Sheet 3 of 15 4

Daily Surveillance Recruirements Log

TECH SPEC 4.2.5.1; 4.3.1.1.9, 10; 4.3.2.1.1d, 3a3, 3c3, 5c, 6d

PRESSURIZER PRESSURE

PARAMETER

INDEPENDENT ACCEPTANCE N/A

PRC0456 PRC0455 CALCULATION VERIFICATION CRITERIA MET

INSTRUMENT PRC0457

PI-456 PI-455 COMPLETED COMPLETED

(MCB OR ERFIS) P1-457

CHANNEL

ACCEPTANCE N/A N/A N/A CHECK

SEE BELOW

CRITERIA 1,2,3

MODE I

C

03I

K6

INSTRUCTIONS

MCB Indicators OR ERFIS

NOTE: Calculations must be done with either the

indications, NOT a combination.

the

If all operable channels are greater than or equal to

criteria, calculations are not required.

acceptance

CALCULATIONS FOR PRESSURIZER PRESSURE

= 4( (#/OOperable = Z7- o a

0300: ZZ3L + NA +

PRESSURIZER

PRC0456 PRC0455 Channels used

PRC0457 PRESSURE

PI-457 PI-456 PI-455 Normally 3)

+ -+ * (# Operable PRESSURIZER

0900: -

PRC0456 PRC0455 Channels used PRESSURE

PRC0457

PI-456 PI-455 Normally 3)

PI-457

+ -+ _ = 4+(# Operable PRESSURIZER

1500: -

PRC045

7

PRC0456 PRC0455 Channels used PRESSURE

PI-456 PI-455 Normally 3)

PI-457

+ - + +(# Operable

2100: -

Channels used PRESSURIZER

PRC0457 PRC0456 PRC0455

PI-455 Normally 3) PRESSURE

pi-457 PI-456

(must meet one of the following):

ACCEPTANCE CRITERIA FOR PRESSURIZER PRESSURE

greater than or equal to

i. Average of operable MCB indicator channels

2205 psig.

than or equal to 2202 psig.

2. Average of operable ERFIS points greater

then the lowest channel

3. If three MCB indicators are not available,

to 2220 psig.

should be greater than or equal

then the lowest channel should

4. If three ERFIS points are not available,

be greater than or equal to 2211 psig.

Rev. 44 Page 16 of 36

OST-1021

JPM SRO-A.I-I

HARRIS

CANDIDATE CUE SHEET

UPON COMPLETION OF TASK)

(TO BE RETURNED TO EXAMINER

INITIAL CONDITIONS:

The Daily Surveillance Logs for 0300 have been completed.

INITIATING CUE(S):

You are to review the logs, noting all errors.

Page 6 of 6

Attachment

Sheet 1 of 415

Daily surveillance Reauirements Log

Rev. 44 Page 14 of 36

OST-1021

Attachment 4

Sheet 2 of 15

Daily Surveillance Reauirements Log

2; 4.5.4.a.1; 4.3.2.1.7b, 8b:4.3.3.6.9 4.1.2.6.a.2, a.3

RWST LEVEL BORIC ACID TANK

I N/A LU-106 LI-161.1 SB TCS7240

1 I L1"992 T U-993

GREATER THAN

CHANNEL GREATER THAN OR EQUAL TO OREQUALTO

74% T

kNOR EQUAL TO 92% CHECK 74%65,F

CHEC

1,2,3 and 4

1,2,3, and4

, 97 qP 66 e4 IF/

4.5.2.a 4.4.9.3

PRZ

SPRAY AT

ECCS VALVE ALIGNMENT

TI-123

181-86 1SI-52 1SI-107 TI-454.1

151-341 1SI-359

PULED TOLESS THAN

D

SHUT AND PULLED TO LOCK WITH OR EQUAL

PULLED TO

TH CONTROL CONTROL POWER OFF T 2°

T 2

YEA OFF

DURING AUX

1, 2, and 3 SPRAY OPS

4.4.3.1; 4.3.1.1.11; 4.3.3.6.5

PRESSURIZER LEVEL

LI-461.1 LI-459A.1 N/A

I-460

CHANNEL

LESS THAN OR

CHECK

EQUALTO90%

R,2. and 3 1

Rev. 44 Page 15 off 365

OST-1021

Attachment

Sheet 3 of 415

Daily Surveillance Reqruirements Log

Dal1y 1 .1.9,10;4.3.2.1.1d, 3a3, 3c3, Sc, 6d

TECH SPEC

PRESSURIZER PRESSURE

PARAMETER

INDEPENDENT

PRC0456 PRC0455 CALCULATION VERIFICATION ACCEPTANCE

INSTRUMENT PRC0457 COMPLETED CRITERIA MET N/A

PI-457 PI-456 Pl-455 COMPLETED

(MCB OR ERFIS)

CHANNEL

ACCEPTANCE SEE BELOW N/A N/A N/A CHECK

CRIEI

1.2,3

I

MODE

0300 17-30 /q6o 7.4- V I 'I

0900 I- U]

1500

II

2100 P-- It

INSTRUCTIONS

Indicators OR ERFIS

NOTE: " Calculations must be done with either the MCB

indications, NOT a combination.

If all operable channels are greater than or equal to the

acceptance criteria, calculations are not required.

CALCULATIONS FOR PRESSURIZER PRESSURE

÷(* Operable

Z7ZO

0300: ZZ. o + AA + -2-10 = PRESSURIZER

PRC0457 PRC0456 PRC0455 Channels used PRESSURE

PI-457 PI-456 PI-455 Normally 3)

- + +

+(4 Operable PRESSURIZER

0900:

PRC0457 PRC0456 PRC0455 Channels used PRESSURE

PI-457 PI-456 PI-455 Normally 3)

__ + + =+(# operable PRESSURIZER

1500:

PRC0457 PRC0456 PRC0455 Channels used PRESSURE

PI-457 PI-456 PI-455 Normally 3)

2100: - + - + = ( Operable PRESSURIZER

PRC0457 PRC0456 PRC0455 Channels used PRESSURE

PI-457 PI-456 PI-455 Normally 3)

following):

ACCEPTANCE CRITERIA FOR PRESSURIZER PRESSURE (must meet one of the

greater than or equal to

1. Average of operable MCB indicator channels

2205 psig.

than or equal to 2202 psig.

2. Average of operable ERFIS points greater

then the lowest channel

3. If three MCB indicators are not available,

than or equal to 2220 psig.

should be greater

the lowest channel should

4. If three ERFIS points are not available, then

be greater than or equal to 2211 psig.

Rev. 44 Page 16 of 3(6

OST-1021

Attachment

Sheet 4 of 415

Daily Surveillance Recuirements Log

INSTRUCTIONS

MCB Indicators OR ERFIS

NOT__E: Calculations must be done with either the

indications, NOT a combination.

to the acceptance

If all operable channels are less than or equal

criteria, calculations are not required.

CALCULATIONS FOR RCS LOOP TAVG

+ ____+ ____- li

+__ Operable

0300: A RCS L

kOOP

TRC0412D TRC0422D TRC0432D Channels used

Normally 3) TAVG

TI-412D TI-422D TI-432D

+ _ =_,__ (# Operable RCS LOOP

0900: _

TRC0422D TRC0432D Channels used TAVG

TRC0412D

TI-422D TI-432D Normally 3)

TI-412D

++ +__-(#Operable RCS LOOP

1500: Channels used

TRC0412D TRC0422D TRC0432D TAVG

TI-412D TI-422D TI-432D Normally 3)

+ TRC0422D + TRC0432D -(# Operable RCS LOOP

2100: TRC0412D Channels u sed TAVG

t'U

lt11- 1

TI-412D TI-422D TI-432D NormaIt .y

of the following):

ACCEPTANCE CRITERIA FOR RCS LOOP TAVG (must meet one

be less than or equal to

i. Average

0

of operable MCB indicator channels must

592.5 F.

than or equal to 593.1'F.

2. Average of operable ERFIS points less

then the highest channel

3. If three MCB indicators are not available, 0

or equal to 591.3 F.

should be less than

then the highest channel should

4. If three ERFIS points are not available,

be less than or equal to 592.3%F.

Rev. 44 Page 17 of 36

OST-1021

Attachment

Sheet 5 of 15 4

Daily Surveillance Requirements Log

4.3.1.1.7,8

4.4.6.2.1.e 4.3.1,1.7, 8

TECH SPEC 4.3.2.1

FLANGE OTAT OPAT PROTECTION AT

PARAMETER ACS PRESSURE LEAKOFF TEMP

TI-41 20, TI-422C. TI-4128, TI-4228, TI-412A, TI-422A,

TI-401 TI-432C TI-4328 TI-432A

INSTRUMENT PI-403.1 PI-402.1

ACCEPTANCE N/A CHANNEL CHECK

CHANNELCHECK

CRITERIA

1. 2, 3 and 4 1, 2, 3and 4 1,2

MODE

'//c

0300

0900

1500

S2100

INSTRUCTION

is not met, perform EST-708, RCS Flow

if RCS flow acceptance criteria

Determination.

Rev. 44 Page 18 of 36

OST-1021

Attachment 4

Sheet 6 of 15

Dailv Surveillance Recalirements Loa

TECH SPEC' 4.4.1.1: 4.3.1,1.12

PARAMETER RCS LOOP FLOWS

INSTRUMENT FRC0414

FI-414 FRC0415 FI-41FRC0416 RCP A

I416 IF1-424 N/A FRC0424 FI0-425

F-45 IF-426I42 RCP B N/A

ACCEPTANCE POSITIVE INDICATION OF FLOW WITH RCP CHANNEL POSITIVE INDICATION OF FLOW WITH RCP CHANNEL

CRITERIA RUNNING INDICATION CHECK RUNNING INDICATION CHECK

MODE 1,2 1 1,22 1

0300 , * .

0900

1500

2100

TECH SPEC 4.4.1.1; 4.3.1.1.12 4.3,1.1.2a, 2b, 5,6

PARAMETER RCS LOOP FLOWS POWER INTERMEDIATE SOURCE

RANGE RANGE RANGE

FRC0434 5FRC435FRC0436F N1,41. NI-42 NI-35 N(-31

INSTRUMENT RCP C N/A NI143, NI-44 NI-36 NI-32

ACCEPTANCE POSITIVE INDICATION OF FLOW WITH RCP CHANNEL

CRITERIA RUNNING INDICATION CHECK CHANNEL CHECK

MODE 1,2 1 1,2 1 (<P-10), 2 2 (<P-6), 3,4,5

0300 f ,zt A* ,,* A/,A*

0900

1500

2100

4.32.1.1e, 3a3, 3c3, 4d, 5c 6d, 6g

TECH SPEC 433361.1.4

4.3.3.6.6

PARAMETER STEAM LINE PRESSURE SG FEED FLOW SG STEAM FLOW

INTRMET P(-474.1,

P)-475, PI-476 Pf-484.1 P149 P-484

F146P144P1-494

P)-485, P--47 I -7 -P19 1475 FI.485 P1-495

ACCEPTANCE CHANNEL CHECK CHANNELCHECK

CRITERIA

MODE 1, 2, 3 and 4 1.2

0300 /..6,' * * .

0900

1500

2100

OST-1021 Rev. 44 Page 19 of 36

Attachment 4

Sheet 7 of 15

Daily Surveillance Renuirements Loa

TECH SPEC 4.3.1.1.13: 4.3.1.1,14: 4.3.2.1.5b, 6c, 10l; 4.3.3.6.7 4.7.1.3.1

PARAMETER SG LEVEL CST LEVEL

INSTRUMENT LI-473. LI-474 LI-483, L1.484 LI-493, LI-494

-LI475.LI-476 [I-485, [1-486 LI-495, [U-496

ACCEPTANCECHANNEL CHECK GREATER THAN OR

CRITERIA EQUAL TO 62%

MODE 1,2, and 3 1, 2. and 3

0300 11 7

0900

1500

2100

TECH SPEC 4.7.1.3.2

PARAMETER ESW TO AFW

1SW-121 1SW.124 ISW-127 1SW.130

ISWM123 ISW.126 1SW-129 1ISW-132

ACCEPTANCE OPEN (only when suppling

CRITERIA AFW pumps)

1,2, and 3

MODE

0200 //'A ,V'/{ A,' NA

0900

9500

1 0

2100 _______________________

OST-1021 Rev. 44 Page 20 of 36

Attachment

Sheet 8 of 15 4

Daily Surveillance Reauirements Loa

INSTRUCTIONS

1 ERFIS is the preferred source for verifying CNTMT AVG TEMP.

If

2 Verify TCV97540 computer point quality code is acceptable.

value for CNTMT AVG TEMP and verify less

acceptable, record the ERFIS

than or equal to 120'F.

MCE indicato.rs

If computer point TCV97540 is not available, verify both

for CNTMT AVG TEMP less than or equal to 120'F.

4

TECH SPEC PLP 114 4.6.1.5 N/A 4.6.1.4 PLP- 11

ROOM

A EDG ELEC EDG ELEC NMCONTAINMENT CONTROL I 305

PARAMETER ROOM 26T 26 AVGEL EOOM PRESSURE E

LB 27 3 TPVR75SSUEENVELOPI

TI-7837

TI-7542 TI-7541 PDI-7680 P0I-7680 TI-7837

T SB A SA BSB AISA B1SB

INSTRUMENT CSA

R EQUAL

LESS THAN OR EQUAL TO 120'F GREATER THAN -1.0 LESS THAN 0O

ACCEPTANCE NO ALARM (< 11 6-F) LOCAL TEMP F

INWG TO 85°

CRITERIA IS NEEDED IF ALARM IS PRESENT

WHENEVER THE

EQUIPMENT IN AN

WHENEVER THE EQUIPMENT IN AFFECTED AREA IS

1.2,3, and 4 .1, 2, 3. and 4

AN AFFECTED AREA IS

REQUIRED TO BE

REQUIRED TO BE OPERABLE

OPERABLE

A,/A iii 1// -0.3 -0.V "70 71

TECH SPEC

PLP-l 14

PLP-I 14

P-Aý

SA ELECT PENET SB ELECT PENE 1A35SA,

ROD CNTRL STE AM

CAB AREA 305 TUNINEL AREA 261 AREA 261 iB35SB 261

PARAMETER FHB EMER EXH AREA

3/2-11 ALB 23/2-8 ALB 23/2-5

TI-6537A1SA TI-6537B1SB ALB 23/3-5 ALB22

INSTRUMENT

ARM

LESS THAN OR EQUAL TO NO ALARM NO AL NO ALARM

ACCEPTANCE 22F) (LESS THAN OR EQUAL TO 104'F)

104'F (L 104-F) (< 12

CRITERIA

WHENEVER THE EQUIPMENT WHENEVER THE EQUIPMENT IN AN AFFECTED AREA IS REQUIRED TO BE OPERABLE

IN AN AFFECTED AREA IS (LOCAL TEMP MUST BE TAKEN IF ALARM IS PRESENT)

MODE

fl_

REQUIRED TO BE OPERABLE

03GO 76 76 11_ I 11 _oI

100900

150090

21002

I

Rev. 44 Page 21 of 36

OST-1021

Attachment 4

Sheet 9 of 15

Daily Surveillance Recauirements Loo

Rev. 44 Page 22 of 36

OST-1021

Attachment 4

Sheet 10 of 15

Daily Surveillance ReauirementS Lop

TECH SPECI ESR 95-00425 ESR 97-00272

ESR 97-00272

COMMITMENT

NEW FUEL POOL HIGH

SPENT FUEL POOL HIGH SPENT FUEL POOL HIGH

PARAMETER TEMPERATURE ALARM TEMPERATURE ALARM

TEMPERATURE ALARM

ALB 23/5-15 ALB 23/5-16

ALB 23/4-16 ALB 23/4-15

INSTRUMENT

NO ALARM

ACCEPTANCE NO ALARM NO ALARM

CRITERIA

1.2, 3, 4. 5 and 6 1,2,3.4,5 and 6

MODE 1,2,3.4,5 and 6

0300

0900

1500

2100

Rev. 44 Page 23 of 36

OST-1021

Attachment

Sheet 11 of 4 15

Daily Surveillance ReQUirements Loa

If a reservoir level computer point is bad, manual reservoir level

NOTE 1:

determination can be performed per OP-163.

is bad, manual reservoir

NOTE 2: If a reservoir temperature computer point

temperature readings can be performed per APP-ALB-002-7-5.

INSTRUCTION

with the permanently

Due to a 3 F instrument inaccuracy associated

0

1.

TSW9114/TSW9115 indicate Ž910 F, obtain

installed reservoir TSWs, if 7 5

- .

local temperature readings per APP-ALE-002-

INSTRUCTION

is only required every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

1. The ECCS leakage outside RABEES reading

(mark as N/A on other days).

Perform on Sunday, Wednesday, and Friday

measured, record the cumulative

2. If any ECCS leakage outside RABEES is

with the locations leaking.

leakrate on Attachment 7, along

Rev. 44 Page 24 of 36

OST-1021

Attachment 4

Sheet 12 of 15

Daily Surveillance Recauirements Loc

Initialing for a

NOTE 1: Meteorological Channel check includes: (1)

ERFIS or verifying data

acceptable quality code if using if

quality is consistent with actual weather conditions

using a Personal Computer(PC) to access the meteorological

and verifying trend

tower, and (2) Recording present values

appears normal.

2 mph or less) it

During calm wind conditions (approximately

between the upper and lower

is normal to see disagreement

indicators. At times the vanes may actually

wind direction

rotate in opposite directions.

the daily channel

The following shall be used for performing

meteorological instrumentation channels:

check of the

wind

On ERFIS observe the points for wind speed,

direction, and differential temperature.

OR

tower and

Using a PC , access the meteorological

wind speed, upper and lower

observe upper and lower

and differential temperature (or

wind direction,

stability class).

"The meteorological instrumentation should only be considered

inoperable if both of the above methods are unavailable.

both a Self Test

NOTE 2: MIMS Channel check should include, as a minimum, channels.

Test of all operable

R and an Audio Monitoring

(Reference 2.6.0.04)

PLP-114 PL

TECH SPEC

METEOROLOGICAL

LOWER UPPER WIND LOWER WIND UPPER WIND AIR

PARAMETER

DIRECTION DIRECTION AT

WIND SPEED SPEED

MMT103 MMTI104 MMT1005 CH

INSTRUMENT MMT1008 MMT1010 MMT1014

COEPTANCE

ACCPT

oi Vo ln Voo n I ao lo* a'e Il V°° I* N

CHANNEL CHECK NOTE 1

CH

CRITERIA Vau nnit Value it Vlenit N

CRTRA Value nit Value Init Value I nit I Value

AT ALL TIMES

MODE

4A /6i .o ~ ~ '

0300

0900

1500

2100

ubT+/-ui-Rev. 44 Page 25 of 3(5

OST-lU4,

Attachment

Sheet 13 of 4 15

Daily Surveillance Recuirements Log

INSTRUCTION

0

less than 71 F, perform Step 7.0.0.05.

1. If battery room temperature is

Rev. 44 Page 26 of 36

OST-1021

Attachment

Sheet 14 of 4 15

Daily Surveillance Recauirements Lop

Rev. 44 Page 27 of 36

OST-1021

Attachment 4

Sheet 15 of 15

Daily Surveillance Recpmirements Loa

NOTE 1: These readings are only required on Sundays. These readings may

be marked N/A on other days.

TECH SPEC 4.1.2.2.a

VCT VALVE SAT EMER BORATION BORIC ACID

PARAMETER GALLERY ROOM XER PUMP

VALVE GALLERY I ROOM

INSTRUMENT LOCAL THERMOMETER

ACCEPTANCE GREATER THAN OR EQUAL TO 65'F

CRITERIA

MODE I, 2 and 3

0300)

0900 (NOTE 1)

1500

2100

TECH SPEC 4.1.2.2.a

BAT TO CSIP SUCTION HEADER PIPE TEMPERATURE

PARAMETER (IFANY OF THESE INSTRUMENTS FAIL, INITIATE CORRECTIVE ACTION AND NOTE IN COMMENTS SECTION. USE

SECONDARY INSTRUMENTS TO SATISFY THE SURVEILLANCE REQUIREMENT)

HT-18753C HT-18753C HT-17538 I HT-18753B HT-18753B HT-187538

INSTRUMENT21 02-2 C1-9 Cl-13 02-3 C2-5

ACCEPTANCE GREATER THAN OR EQUAL TO 655F

CRITERIA

MODE 1,2 and 3

0300

0900 (NOTE 1)

f500

2100 _______ _______

TECH SPEC 4.1.2.2.a

BAT TO C$IP SUCTION HEADER PIPE TEMPERATURE

PARAMETER (THESE ARE SECONDARY INSTRUMENTS. THESE SHOULD BE USED WHEN PRIMARY INSTRUMENTS FAIL.

N/A IF NOT BEING USED.)

HT-187530C HT-18753CC HT-187538 I HT-1B753BB HT-187533 HT-187538B

02-1 02-2 C1-9 Cl-13 02-3 C2-5

ACCEPTANCE GREATER THAN OR EQUAL TO 65°F

CRITERIA

MODE 1, 2 and 3

0300

0900 (NOTE 1)

1500

2100

OST-1021 Rev. 44 Page 28 of 36

Attachment 4

Sheet 1 of 15

Daily Surveillance Reauirements Log

TECH SPEC 4.5, I.I.a.I, 4.5.1.1. b (partial)

ECCS ACCUMULATORS

PARAMETER

CLA A LEVEL CLA B LEVEL CLA C LEVEL

Sampling Not Sampling Not Sampling Not

INSTRUMENT LI- 920 LI- 922 Required

SAtt 6 per LI - 924 LI- 926 Required per LI - 928 LI - 930 Required per

ARt6 L 3 Ar E

ACCEPTANCE between 66 and 96 % indicated level with

CRITERIA less than 9% cumulative level increase (excluding makeup from operable RWST) since last satisfactory sample

MODE 1,2 AND 3 WITH RCS PRESSURE ABOVE 1000 PSIG

Previous Days 72

72--* " 7

Level _ z e e

0300 72Z 77 /. 9 716 7T /<I 73 77

0900

1500

2100

OST-1021 Rev. 44 Page 14 of 36

Attachment 4

Sheet 2 of 15

Dlailv Surveillance Remiirements fLoa

TECH SPEC 4.1.2.6.a.2; 4.5.4.a.1; 4.3,2.1,7b, 8b; 4.3.3.6.9 4.1.2.6.a,2, a.3

PARAMETER RWST LEVEL BORIC ACID TANK

INSTRUMENT LI-0 I LI-991 I LI-992 LI-993 N/A LI161.1 SB

UL0 TCS7240

ACCEPTANCE CHANNEL GREATER THAN OR EQUAL TO GREATER THAN

CCEPTA GREATER THAN OR EQUAL TO 92% CHECK OR EQUAL TO

65'F

MODE 1, 2,3, and 4 1, 2.3 and 4

0300 '77 '?6 97 9q 6',

0900

1500

2100

TECH SPEC 4.5.2.a 4.4.9.3

PARAMETER ECCS VALVE ALIGNMENT PRZ

SPRAY AT

INSTRUMENT ISi-340 1Sk-341 ISI-359 1S-86 1SI-52 ISI-107 T).123

TI-454.1

OPEN AND PULLED TO LESS THAN

ACCEPTANCE LOCK WITH CONTROL SHUT AND PULLED TO LOCK WITH

CRITERIA CONTROL POWER OFF OR EQUAL

POWER OFF TO 6256F

DURING AUX

MODE 1. 2. and 3

SPRAY OPS

0300 I- 1519NA

0900

1500

2100

TECH SPEC 4.4.3.1; 4.3.1.1.11; 4.3.3.6.5

PARAMETER PRESSURIZER LEVEL

INSTRUMENT LI-460 LI-461.1 LI-459A.1 N/A

ACCEPTANCE LESS THAN OR CHANNEL

CRITERIA EQUAL TO 90% CHECK

MODE 1,2. and 3 1

03010 5"___ S-e7

0900

1500

2100O

OST-1021 IRev. 44 Page 15 of 36

Attachment 4

Sheet 3 of 15

Daily Surveillance ReCauirements Loci

INSTRUCTIONS

MCB Indicators OR ERFIS

NOTE: Calculations must be done with either the

indications, NOT a combination.

If all operable channels are greater than or equal to the

acceptance criteria, calculations are not required.

CALCULATIONS FOR PRESSURIZER PRESSURE ,.

+(# Operable PRESSURIZER

0300: 7-_,_o + ____- + ______ - ___

Channels used

PRC0457 PRC0456 PRC0455 PRESSURE

PI-457 pi-456 PI-455 Normally 3)

+ =- +.(# Operable PRESSURIZER

0900: Channels used

PRC0457 PRC0456 PRC0455 PRESSURE

PI-457 PI-456 PI-455 Normally 3)

_ + - + +.(#Operable PRESSURIZER

1500:

PRC0456 PRC0455 Channels used PRESSURE

PRC0457

PI-457 PI-456 PI-455 Normally 3)

2100: _ + _ + = (# Operable PRESSURIZER

PRC0456 PRC0455 Channels used PRESSURE

PRC0457

pi-457 PI-456 PI-455 Normally 3)

PRESSURE (must meet one of the following)

ACCEPTANCE CRITERIA FOR PRESSURIZER

greater than or equal to

i. Average of operable MCB indicator channels

2205 psig.

than or equallto 2202 psig

2. Average of operable ERFIS points greater

the lowest channel

3. If three MCB indicators are not available, then

should be greater than or equal to 2220 psig.

then the lowest channel should

4. If three ERFIS points are not available,

be greater than or equal t '2211 psig.

Rev. 44 Page 16 of 3 6

OST-1021

Attachment

Sheet 4 of 415

K7

Daily Surveillance Reauirements Loa

INSTRUCTIONS

MCB Indicators OR ERFIS

NOTE: Calculations must be done with either the

indications, NOT a combination.

If all operable channels are less than or equal to the acceptance

criteria, calculations are not required.

CALCULATIONS FOR RCS LOOP TAVG

"- -- - - - - -÷(# Operable -

0300: AIA +

TRC0412D TRC0422D TRC0432D Channels

Normally used

3) RCS LOOP

TAVG

TI-412D TI-422D TI-432D

÷(# Operable

0900: Channels used

TRC0422D TRC0432D RCS

TAVG LOOP

TRC0412D Normally 3)

TI-412D TI-422D TI-432D

÷(# Operableused

1500: Channels RCS LOOP

TRC0412D TRC0422D TRC0432D Normally 3) TAVG

TI-412D TI-422D TI-432D

e(# Operable

2100: Channels used RCS LOOP

TRC0412D TRC0422D TRC0432D TAVG

Normally 3)

TI-412D TI-422D TI-432D

one of the following):

ACCEPTANCE CRITERIA FOR RCS LOOP TAVG (must meet

than or equal to

1. Average of operable MCB indicator channels must be less

0

592.5 F.

0

equal to 593.1 F.

2. Average of operable ERFIS points less than or

If three MCB indicators are not available, then the highest channel

3. 0

should be less than or equal to 591.3 F.

4. If three ERFIS points are not 0available, then the highest channel should

be less than or equal to 592.3 F.

Rev. 44 Page 17 of 36

OST-1021

Attachment 4

Sheet 5 of 15

Daily Surveillance Reauirements Loc

TECH SPEC 4.3.2.1 4.4.6.2.1.e 4.3.1.1.7,8

FLANGE OA PT RTE

PARAMETER RCS PRESSURE LEAKOFF TEMP OTT OPT PROTECTION AT

TI-412C, TI-422C, TI-4128. TI-422B, TI-412A, TI-422A,

INSTRUMENT P1-403.1 P1-402.1 TI-401 TI-432C TI-4328 TI-432A

ACCEPTANCE CHANNELCHECK N/A CHANNELCHECK

CRITERIA

12, 3and4 1,2,3and4 1,2

MODE

109001

_ _ _

j2100j_ _ ________ _ _ _ _______

INSTRUCTION

If RCS flow acceptance criteria is not met, perform EST-708, RCS Flow

Determination.

TECH SPEC 4.2.5.1

PARAMETER RCS LOOP FLOWS

FRC0415 FRC0416 FRC0424 FRC0425 FRC0426 FRC0434 FRC0435 FRC0436

FRC0414

INSTRUMENT FI-414 FI-415 FI-416 FI-424 FI-425 FI-426 FI-434 FI-435 FI-436

ACCEPTANCE 98.3% 98.3% 98.3%

CRITERIA

1 1 1

MODE

0300 cS-2 /0,0. 9, /00.761 /C0, 63 i0.7V- 100,71 /00-ý** 1400- 10.Io./

0900

I1500 ___________________

__________________

2100

Rev. 44 Page 18 of 36

OST-1021

Attachment

Sheet 6 of 415

Daily Surveillance Recruirements Loa

4.4.1.1; 4.3.1.A.12

TECH SPEC

RCS LOOP

4.4.1.1; FLOWS

4.3.1.1.12

PARAMETER

FRC0414 FRC0415 FRC0416 RCPA N/A FRC0424

FI-424 FRC0425

FI-425 FRC0426

FI-426 IRCP8 N/A

INSTRUMENT F1-414 FI-415 F1.416

POSITIVE INDICATION OF FLOW WITH RCP

ACCEPTANCE POSITIVE INDICATION OF FLOW WITH RCP RUNNING INDICATION

CRITERIA RUNNING INDICATION

MODE 1,2

0300

09O0

1500

2100

Rev. 44 Page 19 of 36

OST-1021

Attachment 4

Sheet 7 of 15

n.ai Iv Surveillance Re cairements Lea

4.7.1.3.1

TECH SPEC 4.3.1.1.13: 4.3.1.1.14; 4.3.2.1.5b, 6c, 10d: 4.3,3 6.7 4.7.1.3.1

CST LEVEL

PARAMETER SG LEVEL

494 LI-901081 SB

LI-473, LI-474 LI-483, LI-484 L[-493, LI LI-9010A1 SA I

INSTRUMENT LI-475, LI-476 496

LI-485, L-486 LI-495, LI-'

GREATER THAN OR

ACCEPTANCE CHANNEL CHECK EQUAL TO 62%

CRITERIA

MODE 1,2, and 3

,0300,

15001

TECH SPEC 4,7.1.3.2

PARAMETER ESW TO AFW

ISW-l21 1SW-124 1SW-127 ISW-130

INSTRUMENT 1SW-123 1SW-126 1SW.129 1SW-132

ACCEPTANCE OPEN (only when supplying

CRITERIA AFW pumps)

1,2, and 3

NODE

0300 NA ,VA .,v' A

0900

1500

2100

Rev. 44 Page 20 of 36

OST-1021

Attachment

Sheet 8 of 415

Loco

Daily Surveillance Reauirements

INSTRUCTIONS

TEMP.

1. ERFIS is the preferred source for verifying CNTMT AVG

code is acceptable. If

2. Verify TCV97540 computer point quality verify less

AVG TEMP and

acceptable, record the ERFIS value for CNTMT

than or equal to 120'F.

verify both MCB indicators

3. If computer point TCV97540 is not available,

TEMP less than or equal to 1200F.

for CNTMT AVG

NA4.6.1.4 PLP- 114

TECH SPEC pILP-1 14 461

CONTAINMEN EONVEOLROP3

EDG ELEC 8 EDG ELEC CNMT AVG TEMP

PAAMTE

ARMTR ROOM 261 ROOM 261PRSUENVLE30 PDI-7680 T787 T-9

ST-752 TI-7541 PDI-7680

SBB A SA B SB ASA 1B

27/1-3 TCV97540 SA

INTUETALB

NO ALARM (L 16 F) LOCAL TEMP LESS THAN OR EQUAL TO 120NGTO

ACCEPTANCE

CRITERIA IS NEEDED IF ALARM IS PRESENT WHENEVER THE

EQUIPMENT IN Al

WHENEVER THE EQUIPMENT IN

.1,2,3, and 4 AFFECTED AREA

AN AFFECTED AREA IS 1, 2,3, and 4

MODE REQUIRED TO B

REQUIRED TO BE OPERABLE OPERABLE

/ AIM. Jz/ 1 -, */-70 71

0300 /9

0900

1500

PLP-114

TECH SPEC 1A35SA

CNTRL

RODAREA STEAM SA ELECT PENET SB ELECT PENE

PARAMETER FHB EMER EXH AREA CAB 305 TUNNEL AREA261 AREA 261 1S35SB2

ALB 23/2-8 ALA 23f'

TI-6537B1SB ALA 23/3-5 ALB 23/2-11

INSTRUMENT TI.6537A1SA

NO ALARM NO ALARM

LESS THAN OR EQUAL TO NO ALARM

ACCEPTANCE (LESS THAN OR EQUAL TO 104-F)

104°F ( 104IF) (< 122-F)

CRITERIA

WHENEVER THE EQUIPMENT WHENEVER THE(LOCALEQUIPMENT INAN AFFECTED AREA ISREQUIRED TO BE OPERABL

TEMP MUST BE TAKEN IF ALARM IS PRESENT)

MODE INAN AFFECTED AREA IS

REQUIRED TO BE OPERABLE

0300 76 6

-78 /5

0900

1500

2100

Rev. 44 Page 21 of 3E

S... ... 6

OST-1021

Attachment 4

Sheet 9 of 15

Daily Surveillance Reauirements Leo

PLP-1 14

A-SA B-SB IC-SAB SW BSTR MECH & ELEC

CCW PUMPS &HX

CSIP ROOM CSIP ROOM CSIP ROOM B-SB PUMP PENET AREA

AFW PUMPS

236 236 236 236

236 236

ALA 2311-5 ALB 2311-4 ALB 23/1-11 ALA 23/2-9

ALS 2311-6

ALA 23/2-10

ALB 23/1-7

NO ALARM (LESS THAN OR EQUAL TO 104-F)

TO BE OPERABLE

WHENEVER THE EQUIPMENT IN AN AFFECTED AREA IS REQUIRED

IS PRESENT)

(LOCAL TEMP MUST BE TAKEN IF ALARM

PLP-114 4.9.11

NPB A-SA B-SB FUEL POOLS

IVAC CS, RHR, CS, RHR,

JIPRM HVAC HVAC

236 1I0 SPENT FP NEW FP SFP C SFP D

236 19 9

ALB 23/4-17 ALB 23/5-17 ALA 23/4-18 ALE 23/5-18

323/1-9 ALB 23/1-10

"SSTHAN OR EQUAL TO 104' F) NO ALARM (GREATER THAN 23 FT)

IE EQUIPMENT INAN AFFECTED

EQUIRED TO BE OPERABLE WHEN IRRADIATED FUEL IS INTHE POOL

P MUST BE TAKEN IFALARM IS (LOCAL LEVEL MUST BE TAKEN IF ALARM IS PRESENT)

PRESENT)

Rev. 44 Page 22 of 36G

OST-1021

Attachment 4

Sheet 10 of 15

Daily Surveillance Rea-uirements Loa

TECH SPEC / ESR 97-00272 ESR 95-00425 ESR 97-00272

COMMITMENT I

SPENT FUEL POOL HIGH SPENT FUEL POOL HIGH NEW FUEL POOL HIGH

PARAMETER TEMPERATURE ALARM TEMPERATURE ALARM TEMPERATURE ALARM

ALE 23/4-16 ALE 2314-15 ALS 23/5-15 ALB 23t5-16

INSTRUMENT

ACCEPTANCE NO ALARM NO ALARM NO ALARM

CRITERIA

MODE 1,2,3,4,5 and 6 1. 2. 3, 4, 5 and 6 1,2,3,4.5 and 6

1500 _______________

______________

2100

TECH SPEC PLP-114

ESW ELEC EQUIP ROOM ESW PUMP ROOM 261 EDG ROOM 261

PARAMETER 261

A-SA

PARAMETER B-SB A-SA B-SB

INSTRUMENT TEV6588A TEV6588B TEV6592A TEV6592B TDG6BO3A TDG6SO3B

K

ACCEPTANCE LESSTHANOREQUALTO LESS THAN OR EQUAL TO LESS THAN OR EQUAL

CRITERIA 116°F 122°F TO 120WF

WHENEVER THE EQUIPMENT IN AN AFFECTED AREA IS REQUIRED TO BE

MODE OPERABLE

0300

0900

1500

2100

OST-1021 Rev. 44 Page 23 of 36

Attachment

Sheet 11 of 4 15

Daily Surveillance Recnuirements Loa

NOTE 1: If a reservoir level computer point is bad, manual reservoir level

determination can be performed per OP-163.

NOTE 2: If a reservoir temperature computer point is bad, manual reservoir

temperature readings can be performed per APP-ALB-002-7-5.

INSTRUCTION

the permanently

Due to a 3 F instrument inaccuracy associated with

0

1.

installed reservoir TSWS, if TSW9114/TSW9115 indicate :91 0 F, obtain

local temperature readings per APP-ALB-002-7-5.

4.1.2.6b

TECH SPEC 4.7.5

4.5.4.b

RWST AUX RSVR MAIN RSVR LEVEL MAIN RSVR TEMP

PARAMETER AUX RSVR LEVEL TEMP

TEMP

TSW9114 LSC8750A LSC8750B

TCT7110 LSC8752A LSC8752B TSW9115

INSTRUMENT

>40'F GREATER THAN OR GREATER THAN OR

  • 94'F EQUAL TO 215 FT S94'F 2

NOTE

iACCEPTANCE AND EQUAL TO 250 FT NOTE 2 NOTE I

CRITERIA < 125°F NOTE I

MODE

0300

12100

INSTRUCTION

every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

1. The ECCS leakage outside RABEES reading is only required

Sunday, Wednesday, and Friday (mark as N/A on other days).

Perform on

the cumulative

2. If any ECCS leakage outside RABEES is measured, record

with the locations leaking.

leakrate on Attachment 7, along

Rev. 44 Page 24 of 36

OST-1021

Attachment 4

Sheet 12 of 15

nsilv Surveillance Reauirements Lao

NOTE 1: Meteorological Channel check includes: (1) Initialing for a

acceptable quality code if using ERFIS or verifying data

quality is consistent with actual weather conditions if

using a Personal Computer(PC) to access the meteorological

tower, and (2) Recording present values and verifying trend

appears normal.

During calm wind conditions (approximately 2 mph or less) it

is normal to see disagreement between the upper and lower

wind direction indicators. At times the vanes may actually

rotate in opposite directions.

The following shall be used for performing the daily channel

check of the meteorological instrumentation channels:

On ERFIS observe the points for wind speed, wind

direction, and differential temperature.

OR

Using a PC , access the meteorological tower and

observe upper and lower wind speed, upper and lower

wind direction, and differential temperature (or

stability class).

The meteorological instrumentation should only be considered

inoperable if both of the above methods are unavailable.

MIMS Channel check should include, as a minimum, both a Self Test

NOTE 2:

R and an Audio Monitoring Test of all operable channels.

(Reference 2.6.0.04)

fl

I

_________________

PLP-1 14 PLP-114

TECH SPEC

METEOROLOGICAL

MIMS

PARAMETER LOWER UPPERWIND LOWERWIND UPPERWIND AIR

AT

WIND SPEED SPEED DIRECTION DIRECTION

I

II-

MM1004

MMI01 MMT00S ALL

MMT1010 MMT1014 MMT1013 MMT1004 MMT100 CHANNELS

INSTRUMENT MMT1008

- -CHANNEL

CHANNEL CHECK NOTE 1 CHANNEL

CHECK

ACCEPTANCE

NOTE2

CRITERIA Value I nit Value I Init I Value I lnit I Value nit Value nit Value nit -11

I

1,2

lvi'.J L a

AT ALL TIMES 1,2

0300o 9.4,0 ih

1 0 14.1 . 1l!5 . .I

2100

Rev. 44 Page 25 of 36

OST-1021

Attachment 4

Sheet 13 of 15

Dailv Surveillance Reauirerxents Log

TECH SPEC PLP-114

EDG HVAC ROOM 280 EDG HVAC ROOM 292 DFOST BLDG TANK AREA

A-SA B-SB 1 SA B242 1-F 236

AARABE-A

NIQlTDI IttAAi~MT LOCAL THERMOMETER

LESS THAN OR LESS THAN

ACCEPTANCE LESS THAN OR EQUAL TO LESS THAN OR EQUAL TO 122F EQUAL TO OR EQUAL VERIFIED

CRITERIA 118F 122F TO 104'F

MODE WHEN THE EQUIPMENT INTHE AFFECTED AREA IS REQUIRED TO BE OPERABLE

0300

1500

2100

INSTRUCTION

1. If battery room temperature is less than 71'F, perform Step 7.0.0.05.

TECH SPEC PLP-114 4.3.1.1,2.a

ELECT SWITCHGEAR BATTERY ROOM 286

PENETRATION ROOM 286 OS1000

PARAMETER AREA 286 305

A-SA B-SB

B-SB A-SA B-SB

A-SA

INSTRUMENT LOCAL THERMOMETER N/A

LESS THAN

ACCEPTANCE LESS THAN OR LESS THAN OR OR COMPLETED VERIFIED

CRITERIA EQUAL TO 104WF EQUAL TO 90'F EQUAL TO SAT

85°F

WHENEVER THE EQUIPMENT INAN AFFECTED AREA IS REQUIRED TO BE I above 15%

MODE OPERABLE Power

0300

0900

1500

____ ______ ______ _____

2100

OST-1021 Rev. 44 Page 26 of 36

Attachment 4

Sheet 14 of 15

Daily Surveillance Recuirements Loa

TECH SPEC PLP-114

E-6 ROOMS 261 AUX TRANSFER PANEL ROOM 286 Plc ROOMS 286

PARAMETER B-SB A-SA 3

B-SB 17,19 18

A-SA

INSTRUMENT LOCAL THERMOMETER

LESS THAN OR EQUAL

LESS THAN OR EQUAL TO 104-F L 8

THOR VERIFIED

ACCEPTANCE

CRTO85'F

MODE WHENEVER THE EQUIPMENT INAN AFFECTED AREA IS REQUIRED TO BE OPERABLE

0300

0900

1500

2100

TECH SPEC

PLP-114

I

PARAMETER ACP 286

AH-15 VENTILATION ROOM 11 ARP ROOM 305

LOCAL THERMOMETER

INSTRUMENT

LESS THAN OR EQUAL

ACCEPTANCE LESS THAN OR EQUAL TO 90° ESS

- THAN OR EQUAL TO 104°F TO 85'F

CRITERIA

WHENEVER THE EQUIPMENT IN AN AFFECTED AREA IS REQUIRED TO BE OPERABLE

MODE

Rev. 44 Page 27 of 36

OST-1021

Attachment 4

Sheet 15 of 15

IfAii qrvoii

,, acPsnivsrT,

... tnc

NOTE 1: These readings are only required on Sundays. These readings may

be marked N/A on other days.

TECH SPEC 4.1.2.2.a

PRMTRXFER

VCT VALVE BAT PUMP EMER

MRBAfNBORATION BORIC ACID

GALLERY ROOM VALVE GALLERY VALVE RM XFER PUMP

11 AL ROOM

INSTRUMENT LOCAL THERMOMETER

ACCEPTANCE GREATER THAN OR EQUAL TO 65°F

CRITERIA

MODE 1, 2 and 3

0300)

0900 (NOTE 1)

1500

2100

TECH SPEC 4.12.2.a

BAT TO CSIP SUCTION HEADER PIPE TEMPERATURE

PARAMETER (IFANY OF THESE INSTRUMENTS FAIL, INITIATE CORRECTIVE ACTION AND NOTE INCOMMENTS SECTION. USE

SECONDARY INSTRUMENTS TO SATISFY THE SURVEILLANCE REQUIREMENT)

INSTRUMENT HT-18753C HT-18753C HT-IS753B HT-i8753B HT-18753B HT-18753B

C2-I C2-2 Cl-9 Cl-13 C2-3 C2-5

ACCEPTANCE GREATER THAN OR EQUAL TO

65'F

CRITERIA

MODE 1, 2 and 3

0300

2100

TECH SPEC 4.1.2.2.a

BAT TO CSIP SUCTION HEADER PIPE TEMPERATURE

PARAMETER (THESE ARE SECONDARY INSTRUMENTS. THESE SHOULD BE USED WHEN PRIMARY INSTRUMENTS FAIL.

N/A IFNOT BEING USED.)

HT-18753CC HT-18753CC HT-18-53BB HT-18753bB HT-18753BB HT-187538

INSTRUMENT C2.1 C2-2 l1-9 Cl-13 C2-3 C2-5

ACCEPTANCE GREATER THAN OR EQUAL TO 65'F

CRITERIA

MODE 1.2 and 3

0300

0900 (NOTE8 I

1500

2100

_ OST-1021 Rev. 44 Page 28 of 36

JPM RO-A.I-I

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM RO-A. 1.1

Determine Rod Misalignment Using

Thermocouples

CANDIDATE:

EXAMINER:

Page I of 8

JPM RO-A.1-I

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Determine Rod Misalignment Using Thermocouples

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

IMPORTANCE: SRO NA RO 4.4

KA: 2.1.19

KA STATEMENT: Ability to use plant computer to obtain and evaluate

parametric information on system or component status.

is

TASK STANDARD: Determines Shutdown Bank A Rod C9 is misalignment

NOT verifiable using incore thermocouples

SIMULATOR IN PLANT

PREFERRED EVALUATION LOCATION:

PERFORM SIMULATE

PREFERRED EVALUATION METHOD:

REFERENCES: AOP-001, Malfunction of Rod Control and Indication System

10 MINUTES TIME CRITICAL: No

VALIDATION TIME:

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

SAT UNSAT

PERFORMANCE RATING:

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

JPM RO-A.l-l

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

list of thermocouple

Provide candidate with values from JPM Attachment which contains

how information will be

temperatures in alphanumeric order after candidate states

obtained.

System"

AOP-001, "Malfunction of Rod Control and Indication

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

performed. All control

I will explain the initial conditions and state the task to be

any required communications. I

room steps shall be performed for this JPM, including

when directed or asked by

will provide initiating cues and reports on other actions

your assigned task. To indicate

you. Ensure you indicate to me when you understand

the handout sheet I provide you.

that you have completed your assigned task, return

INITIAL CONDITIONS:

The plant is operating at 100% power.

System," is being performed in

AOP-001, "Malfunction of Rod Control and Indication

Bank A Rod C9 may be misaligned

response to suspected indications that Shutdown

by more than 12 steps.

INITIATING CUE(S):

the Core Exit Thermocouples support

You have been directed to determine whether

Attachment 1,"Indications of

the indication of a misaligned rod per AOP-001,

Misaligned Rod."

Page 3 of 8

JPM RO-A.1-1

HARRIS

<> START TIME:

  • DENOTES CRITICAL STEP

STANDARD NOTES SAT /

JPM PROC ELEMENT

STEP STEP UNSAT

NA Obtains procedure Obtains current copy of

AOP-OO1, Attachment I

NOTE: EXAMINER'S ANSWER KEY IS

INCLUDED, WHICH INDICATES THE

INFORMATION THAT THE CANDIDATE

SHOULD DETERMINE.

PROCEDURE STEPS LISTED ON THIS JPM

IDENTIFY THOSE STEPS AS LISTED ON THE

ATTACHMENTS.

2 Att I Greater thn1 0 ifrne Obtain current copy of

between thermocouples AOP-001, Attachment 2

adjacent to the misaligned rod

and the average of symmetric

thermocouples (Perform

Attachment 2.) Uigcr

Using core grid drtcltto

Critical

  • 3 Att 2 - 1 Determine thermocouple

location(s) adjacent to the map, determines determine

misaligned rod using core thermocouple adjacent

grid map (Sheet 1), and adjacent to Rod C9 thermocouple

circle locations(s) in Table is in location C8 location to allow

above. These thermocouple(s) * Circles location C8 determining

on table which

are affected. thermocouples

are symmetric.

Only

determination is

critical.

Page 4 of 8

JPM RO-A.I-l

HARRIS

NOTES SAT/

JPM PROC STANDARD

ELEMENT UNSAT

STEP STEP

Att 2-2 Record values for all operable Records following

4

affected and symmetric values for affected and

thermocouples using the symmetric

RVLIS Console or ERFIS. thermocouples:

Symmetric thermocouples are . C08 (aff) - 602'F

those in the same row. H1I3 (sym) - 608'F

  • N08 (sym) - 608'F
  • H03 (sym) - 609'F

CUE (PR VIDEDAFTER CANDIDATE STATES

THEY MUST OBTAIN THERMOCOUPLE

TEMPERATURES FROM RVLIS CONSOLE OR

ERFI)): PROVIDE TEMPERATURES WHICH

CANDIDATE REQUESTS BASED ON

THERMOCOUPLE LOCATION FROM JPM

ATTACHMENT.

Critical to

4tr Determine the average of -Determines average of

symmetric thermocouples, symmetric correctly

thermocouples - determine the

for each affected

608.330 F average of the

thermocouple.

symmetric

thermocouples

for comparison to

the affected

thermocouple.

Determines Core Exit Critical to

"*6 Att I Determine if Core Exit

Thermocouples do determine that

Thermocouples support

NOT support the thermocouple

indication of misaligned rod

indication of indications do not

misaligned rod due to support

difference between indication of a

affected thermocouple misaligned rod.

and symmetric

thermocouple being

<IO°F (6.330F)

STASK COMPLETE

STOP TIME:

Page 5 of 8

JPM RO-A. I-I

HARRIS

JPM RO- A.I1.1 ATTACHMENT

INCORE THERMOCOUPLE TEMPERATURES

TEMP THERMOCOUPLE TEMP

THERMOCOUPLE

(in OF) LOCATION (in 0F)

LOCATION 622

ABANDONED HO9

A08

Hl1 618

B05 590

H13 608

B10 588

602 Hi1 603

C08

J02 604

C12 605

J10 615

D03 608

611 J12 ABANDONED

D05

K03 604

E04 606

610 K05 611

E07

K08 615

E08 619

618 K1 ABANDONED

El0

L06 615

E12 614

L08 614

E14 604

L12 609

F03 ABANDONED

614 L14 ABANDONED

F05

M03 606

F09 614

615 M09 618

Fll

Ml 617

F13 608

N04 609

G1u ABANDONED

N06 610

G02 604

611 N08 608

G06

N10 608

G08 621

P07 607

G15 603

609 P08 604

H03

R07 613

HUD 616

Page 6 of 8

JPM RO-A.1-I

HARRIS

ANSWER KEY FOR JPM RO-A.1-1

Attachment 2

Sheet 2 of 2

Affected and Symmetric Thermocouple Locations

NOTE

B10. E07, K08, and P08 have no symmetric locations.

GRID I II IlI IV

TRAIN A B A B A B A B

A08* H15

G01 * G15 R07

S L B05 __E14 L14'

S0 _C08 H13 N08 H03

M C D C12 N04 M03

M A E04 D05 E12 M11 L12

E T H11 E08 L08 H05

T I F05 F11 E10 Kl1 K05 L06

R 0 F03* F13 N10 N06 K03

I N G06 F09 JIG

C S GOB H09

G02 J02 P07

M09 J12"

1. Determine thermocouple location(s) adjacent to the misaligned rod using core grnd map

(Sheet 1), and circle locations(s) in Table above. These thermocouple(s) are affected.

2. Record values for all operable affected and symmetric thermocouples using the RVLIS

Console or ERFIS. Symmetric thermocouples are those in the same row,

"* Affected TC #1 CPC 6902 )Syrnmetric TC(s) _3_(608)-N._08 (.6_0_8) -- 03(609)

"* Affected TC #2 ------ Symmetric TC(s) (AVERAGE = 608.67)

  • Affected TC #3 ....... Symmetric TC(s) ..................
  • Affected TC #4 .................. Symmetric TC(s) -----

3. Determine the average of symmetric thermocouples, for each affected thermocouple.

Page 7 of 8

JPM RO-A, I-I

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is operating at 100% power.

AOP-001, "Malfunction of Rod Control and Indication System," is being performed in

response to suspected indications that Shutdown Bank A Rod C9 may be misaligned

by more than 12 steps.

INITIATING CUE(S):

support

You have been directed to determine whether the Core Exit Thermocouples

of

the indication of a misaligned rod per AOP-001, Attachment I, "Indications

Misaligned Rod."

Page 8 of 8

JPM COM-A. 1-2

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM COM-A. 1-2

Perform a Manual Power Range Heat Balance

Calculation

CANDIDATE:

EXAMINER:

Page I of 21

JPM COM-A. I-2

HARRIS

REGION II

,-I>

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Perform a Manual Power Range Heat Balance Calculation

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

IMPORTANCE: SRO 4.6 RO 4.4

KA: 2.1.25

KA STATEMENT: Ability to obtain and interpret station reference materials

such as graphs, monographs, and tables which contain

performance data.

TASK STANDARD: Heat balance has been calculated within allowable tolerance

SIMULATOR IN PLANT

PREFERRED EVALUATION LOCATION:

PERFORM SIMULATE

PREFERRED EVALUATION METHOD:

REFERENCES: * OST-1204, Power Range Heat Balance, Manual Calculation, Daily

Interval, Mode I (Above 15% Power)

a Steam Tables

X-S MINUTES TIME CRITICAL: No

VALIDATION TIME:

CANDIDATE:

START TIME: FINISH TIME:

MINUTES

PERFORMANCE TIME:

UNSAT

PERFORMANCE RATING: SAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 21

JPM COM-A. I-2

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

"* Provide candidate with Attachment which contains collected data and required forms

to fill out.

"* Examiner's Answer Key is also included as Attachment.

Daily Interval, Mode 1

"* OST-1204, Power Range Heat Balance, Manual Calculation,

(Above 15% Power)

"* Steam Tables

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

room steps shall be performed for this JPM, including any required communications. I

will provide initiating cues and reports on other actions when directed or asked by

you. Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

The plant is operating at approximately 100% power. ERFIS is out-of-service and is

expected to be out for an extended period of time.

OST-1204, Power Range Heat Balance, Manual Calculation, Daily Interval, Mode 1

(Above 15% Power) is to be performed to meet the periodic surveillance requirement

for Technical Specification 4.3.1.1, Table 4.3-1, Item 2a.

Steam Generator Blowdown is isolated.

I&C Technicians have collected all necessary data for the calculation.

INITIATING CUE(S):

You have been directed to perform OST-1204, Power Range Heat Balance, Manual

Calculation, Daily Interval, Mode 1 (Above 15% Power), by completing Attachment

5, "Calorimetric Worksheet," and Attachment 6, "Certifications and Reviews."

NOTE: The Examiner will provide you with completed Attachments 1-4 and copies

of Attachments 5 and 6 for you to complete.

Page 3 of 21

JPM COM-A. 1-2

HARRIS

START TIME:

  • DENOTES CRITICAL STEP

ELEMENT STANDARD NOTES SAT/

JPM PROC UNSAT

STEP STEP

1 NA IObtains procedure Obtains current copy of

OST- 1204

NOTE: FOLLOWING JPM STEPS DESCRIBE

HOW ATTACHMENTS 5 AND 6 OF OST-1204 ARE

TO BE FILLED OUT.

EXAMINER'S ANSWER KEY IS INCLUDED.

BOLDED ITEMS WITH SHADED BACKGROUND

ARE CONSIDERED TO BE THE CRITICAL

STEPS REQUIRED TO SUCCESSFULLY

COMPLETE THIS JPM.

PROCEDURE STEPS LISTED ON THIS JPM

IDENTIFY THOSE STEPS AS LISTED ON THE

ATTACHMENTS.

1) Fills in SG Pressures Critical to

from Art 3 as SG A

Ia Exit Enthalpies:

- 900, SG B - 890, determinetosteam

  • Steam Tables Lookup: SG C - 900 enthalpy

Saturated Steam, determine power

2) Looks up liq

Liquid Enthalpies level.

enthalpy for SG

pressures as SG A Note liquid

526.7, SGB enthalpy value is

5259.0+0+/-.2 NOT critical

(interpolation since it will be

-

526.7 r multiplied by

sG,

3) Looks up steam zero in next step.

enthalpy for SG

requiired,

pressures as SG A

- 1196.4, SG B

1196.7+0.2

(interpolation

required), SG C

1196.4

Page 4 of 21

JPM COM-A. 1-2

HARRIS

PROC ELEMENT STANDARD NOTES SAT/

JPM

UNSAT

STEP STEP

  • 3 Att. 5 * Calculate SG Exit Determines SG exit Critical to

enthalpies, by accurately

lb Steam Enthalpies calculate exit

multiplying liq

enthalpy by zero and enthalpy to

then substracting from determine power

steam enthalpy (same level.

value as steam

enthalpy), as SG A Note that

1196.4, SG B tolerance is

1196.7+0.2, SG C carried forward.

1196.4

  • 4 Att. 5 - 2 Feedwater Enthalpy (Steam Using temperature Critical to use

value of feedwater, temperature and

Tables Lookup) not pressure of

determines enthalpy of

sat liquid at 440'F to feed to determine

be 419.0 enthalpy.

  • 5 Att. 5- 3 Enthalpy Rise Across the Determines enthalpy Critical to

rise across SGs, by accurately

Steam Generators calculate

subtracting FW

enthalpy from SG exit enthalpy rise to

enthalpy, as SG A determine reactor

777.4, SG B power.

777.7+0.2, SG C

777.4 Note that

tolerance is

carried forward.

1) Fills in FW Flows Critical to

from Art 3 as SG A

- 4.246, S6 B calculate SG

4.223, SG C - 4.255 power to

2) Determines SG determine reactor

powers, by power.

multiplying FW

Flows by SG Note that

enthalpy rise, as SG tolerance is

A- 3300.84, SG B - carried forward

3284.23+/-0.85, SG C and adjusted due

-3307.84 to multiplication.

Page 5 of 21

JPM COM-A. 1-2

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP UNSAT

STEP

Critical to

  • 7 1 Att.5-5 Calculate Total Reactor Determines total Critical to

reactor power, by accurately

Power calculate total

adding the SG powers

and subtracting RCP reactor power to

heat input, as determine reactor

9850.60+0.85 power.

Note that

tolerance is

carried forward.

  • 8 1 Att. 5 - 6 Convert Mbtu/hr to MWth Converts to thermal Critical to

power, by dividing accurately

total reactor power by convert to

a conversion factor, as determine reactor

2886.96+0.25 power.

Note that

tolerance is

carried forward

and adjusted for

division.

  • 9 Att.5-7 Calculate Percent of Rated Determines percent Critical to

reactor power, by accurately

Thermal Power convert to

dividing thermal power

by rated thermal determine percent

power, as 99.6+0.1 reactor power.

Note that

tolerance is

carried forward

and adjusted for

division.

Page 6 of 21

JPM COM-A. 1-2

HARRIS

I-"

SAT!

ELEMENT STANDARD NOTES SAT /

JPM PROC

STEP STEP UNSAT

"*10 It. 5 --8 Power Range NI 1) Fills in highest and Critical to

lowest indicated PR accurately

Surveillance

channels from Att 3 determine

as 100 and 99.5 difference

2) Determines between

difference between indicated and

indicated and actual power to

calculated power, determine if PR

by subtracting NI channels

calculated from require

indicated, as adjustment.

Highest Indicated

0.4+0.1% and Note that

Lowest Indicated tolerance is

(-)0.1+0.1% carried forward.

Signs Attachment 5

II Art 5 Perf I Sign Attachment 5 as

Performer

2 12 -Caluato Verfide

aculalonVeriiedcalculation verification

-quests of

CUE: FOR PURPOSES OF THIS JPM OiNLY,

VERIFICATION IS NOT REQUIRED.

13 Att 6 Check OST 'performed for Checks periodic

periodic surveillance surveillance

14 Fill in plant conditions Fills in plant conditions

as 100% power, Mode I

15 S9-ign / date ýcompletion of Signs and dates

OST completion of OST

TASK COMPLETE

STOP TIME:

Page 7 of 21

JPM COM-A. 1-2

HARRIS

ANSWER KEY FOR JPM COM-A1-2

Attachment 5

Sheet 1 of 2

Calorimetric Worksheet

i. Calculate Steam Generator Fxit Enthaipies

a. Steam 'Tables Lookup: Saturated Steam, Liquid EnthalPies

Liq. Enthalpy {h:) Stm. Enthalpy 0,,ý

SG Pressure

900 526.7 bt/m 1196.4 btu/:bm

SG A: 0 psia

890 525.0+/-0.2 bt!/lhm, 1196.7+/-0.2 btu,/lhml

SG B: 890 osia

900 -*+

526.7 bt/l/bm, 1196.4 btu4/7bm

SG C: - psia

b. Calculate SG Exit Steam Enthalpies

Stm. Enthalpy Liq. Enthalpy Exit Enthalpy

(h,)

1196.4 bbu/lbm

1196.4 0.00 x 526.7

SG A: 1.00 x +

1196.7+/-0.2 btu/lbm

SG B: 1.00 2 196.7+/-0.2+ 0. 00 5,25.0+/-0.2 1196.4 btuIbm

1.OO x 1196.4 + 0.00 x 526.7

SG C:

2. Feedwater Enthaloy (StmTables Lookup)

?W Enthavpy 'hrN}

--W(TempýPressý 419.0

btu/Ibm

440 1080

FW AvRrý F G

3. Enthaloy Rise across the Steam Generators

Exit Enthaloy FW Enthla..py A Enthalpy

ýh,,.-) 777.4

1196.4 419.0 bvu/lbm

SG A: 777.7+/-0.2

419.0 ht:/]. bm

Sr R: 1196.7+/-0.2 777.4

1196.4 419.0 Dti bm

SG C.: _ _ __ _

ANSWER KEY FOR JPM COM-A1-2

Page 8 of 21

JPM COM-A. 1-2

HARRIS

Att achment 5

Sheet 2 ,f 2

Cal4r.metri wrksheet

Wc

4. -Steam Generator Powers

FEW Flow A Enahalpy (Mbtu/hrý

(MPPH) (bcu/lbmi

4.246 777.4 3300.84

4.223 x 777.7+/-0.2

x

777.4 3_ 0 7 .8__

_zhM b'u ,

4.255

-. Calculate Total Reactor Power

3300.84 3300.23+/-0.85 3307.84 9850.60+/-0.85 ?blhttu11h

+/- + 42.31

6. Convert Mbtu/hr to MW ;,

2886.96+/-0.25

9850.60+/-0.85 Mbtu/hr 3.4121 Mbtu/hrIMW:. MW-

7. Calculate Percent of Rated Thermal Power

2886.96+/-0.25 Mr' x 100 99.6+/-0.1  % RT P

2900 MW-I,

8. Power Range NT Sujrveillance

100.0 99.6+/-0.1 0.4+/-0.1

C;al;' d Power 3'

Hi-ghes -Z N: A)

99.6+/-0.1 -0.1+/-0.1

99.5

Lowest PR N: (U) "Cal-'d Power A%

C2ANDTDA' TE SIGN

perf rtned By:

N/A

Verified 5v:

ANSWER KE A1-2

Page 9 of 21

JPM COM-A. 1-2

HARRIS

ANSWER KEY FOR JPM COM-A1-2 At*achmC-,. 6

Sheet 1 o: I

Cert ficat"ons and Reviews

x

This OST was performed as a: Periodic Surveillance Requirement:

......

Post Maintenance operability Test.:


Redundant Subsystem Test:

100% power Mode: 1

Plant conditions:

By: CANDIDATE SIGN Date e: CURRENT

CRRN

ost, completed

CURRENT

OST Performed By:

Initials Name (Print)

initials Na-e !Print)

BJ Bob Jones

SS Samuel Snead

CANDIDATE INITIAL / PRINT NAME

Actions/Except.i.ons:

General Comments/Recommefndationsiorrective

Pales used:

09T Completed wkth No EXCEPTIONS /X*EP.C...c.

ty2 it: SCO

the f.inal revý.ew Sianature, tfiS tecomes a QA R""CRD

After receivil,

s10Lold be sv,: dto Dcl~ent Servi47&S.

ANSWER KEY FOR JPM COM-A1-2

Page 10 of 2I

JPM COM-A. 1-2

HARRIS

ATTACHMENT FOR JPM COM-AI-2

(DATA COLLECTED) Att:achmt~enl 1

Sh~eet 1 of 1

calibration Data Sheet

INST ID NO. CAL D1UE PATE

INST/MCDEL DESCRIPTION

VM164 9/20/02

precision DVM

0.04% accuracy or better

tex. Eluke Model 45"

Precision DVM

VM226 10/02/02

0.04t accuracy or betC*r

(ex. Fluke Model 15]

Page I I of 21

JPM COM-A. 1-2

HARRIS

ATTACHMENT FOR JPM COM-A1-2

(DATA COLLECTED) Att*achment 2

Sheet I of 3

Collection of Field Inputs

NI drawers

NOTE: - Power Range NI readings should be recorded at the

- with the meter rate set to q:,0w, and should reflect: cea't

values during the recording interval.

I Power ranfle N1 readings shouud be collected acprcXamately

halfway throug:. toe data gathezr'tg process.

Page 12 of 21

JPM COM-A.l-2

HARRIS

ATTACHMENT FOR JPM COM-AI-2

(DATA COLLECTED)

Attachmen: 2

Sheet 2 of 3

collection of Field Inputs

stea;m

NOTE: e +/-n the followinglf table, only one of the three redundant

i.ne are recored.

pressure sgnals fo- each main steamn

SOnl.y one feedwater pressure signal is required.

voltages t, )-'Cee decimal places.

  • Record all

Page 13 of 21

JPM COM-A.HARRIS1-2

ATTACHMENT FOR JPM COM-AI-2

(DATA COLLECTED) A

.*tachmenZ

3 of 23

S heet

Collection of Field Inputs

"* Record all voltages to three decimal places.

NOTE:

scaled from 1 - 5 volts.

"* All rtransmftter signals are

signal voltages are required.

  • A"l trasmitter

TURBINE BLDG. 286' ELEVATION

STerminals Voltage

ERFIS MUX Temn Block (Pos: eg ) 1 -5 V)

Transmitter

TE-2105 54B R iF (07: 08) 2.490 V

FWTemp

Loop A

TE-2106 54B R iF (10:11) 2.498 V

FW Temp

Loo B

54B R IF (13: 14) 2.500 v

FW Temp TE-2107

Loo C

FT-2007A 54B R E (19: 20) 4.076 v

Fw Fow

Loop A

54B R lE (22: 23) 4.048 V

(Both values FT-2006A

required)

FIN Flow FT-2007B 54B R 1E (16 : 17 ) 4.021 v

(Both values FT-2006B 54B R lF (10:11) 4.047 V

required)

FW Flow F-2007 54B FI*E 13 :14 ) 4-067 v

LoopC

54B R 1E (10 : 11 ) 4.087 v

(Both values FT-2006C

required)

Page 14 of"21

JPM COM-A.

HARRIS1-2

ATTACHMENT FOR JPM COM-A1-2

(DATA COLLECTED)

A-Zachmen- 3

Sheet 1 of 2

Field Inut DeveloPmenfl

i. Steam Generator Pressures

SG A Pressure

6.810 Ix 130. * 14.7

900 Psia

vo t

SG B Pressure

6.733 ] x 130. I.I . 7 890 Ps;ia

SG C Pressure

6.820 900 PsDia

L

Ix 130. '4.7

2. Feedwater Pressure

14.7 = _ 1080

2.490 ._0 I x 37S. Psia

AV. Tn

Avg TransmiLtzpr Signal

2.490 2.498 + 2.500 3 - 2.496

Tev1 Siqna2

.AJ

7T82 OS Volts "T.72107 Vo1t7

FW Average Temperature

2.496 440 e

Fr AN;

Page 15 of 21

JPM COM-A.

HARRIS1-2

A~feH9=E~J M-(-

Attachment

Sheet 2 of 23

4. Feedwater Flow AP

SG A Avq Transmiltter Sig/w

4.076 ___ _ "  ; 2. 777A

4.062

v 7p

Val ts

FTy'rOC A VOxts F 2ý0A V*lV:

SG A FW Flow AP

4.062 1.0 x 298.375

912.79 I nwC

sc. A All FW VoIt.

SG B Ave Transmitter Signal

4.021 4.047 2. 4.034 VC, tS

aC 7, 7Ng 77;7~j

fl-2007B VOlitJ nT.2 (a Volts

SG B FW Flow AP

4.034 1.0 x 296.475

899.39

SGB CowA*

Inwc

SG S AvgVý V Oltt"

SG C Avg Transmitter Signal

4.067 4.087 S.2.

4.077 Volts

  • gC 2 Avq3 Fw Volts

Fr-2000c VcItn TFl2006C Volts

SG C FW Flow ArP

4.077 1.0 x 297.17S

914.30

C' -.".'¢l; % Snw c

S3 C AVg FW Voltlt

By:

Bob Jones

pertcrmredi

Samuel Snead

Verified By:

Page 16 of 21

JPM COM-A. 1-2

HARRIS

ATTACHMENT FOR JPM COM-A1-2

(DATA COLLECTED)

Attachment

Sheet 1 of 41

Feedwater Flow Worksheet

1. Feedwater Venturi Expansion Coefficient

fa 0.99881

o.172682- 4 440 *F

0.25,026E-8 * 440 'F

FI' Av,

- FW Aq

1.006409

2. Feedwater Fitid Densi:'!

i.0 / Spec Vol 440 1080 ) Stnm Tables lookup:

FW Avq "1 idpsta

EW 1

P7. 51.92 (ibm,/ft

3. Feedwater Flows

7q Flow, SG A

1.006409 , 912.79 51.92

FW A 1.93800E-2 . A Fow ll F

7- (I fwc*

FW A =

4.246

FW Flow, SG B

FWq B = .94180E-2

1.006409 s

899.39

B Flow

F A

51.92

fa

ix[ ','

WB.

4.223

FW Fiew, SG C

1.006409 914.30 . 51.92

p,

4.255 :m*,

Bob Jones

performed By:

V'ri fiel By:

Samuel Snead

Page 17 of 21

1PM CQM-A.I1-2

HARRIS

ATTACHMENT FOR JPM COM-A1-2

(TO BE COMPLETED AND RETURNED TO EXAMINER)

Attachment 5

Sheet 1 at 2

Calorimetric worksheet

i. Calculate steam C~eneratar Exit Enthalpies

P2ables [,ookuo: gaurre Seam, Llmild EnthalptCS

a. Steam

L:.a . 7En1tha-py ýhrý St~m. Entýhalpy

S", Pressilre

btul/lbm, br. u/Ibm,

SG A:

________psia

b t u / 1bnw, btu-/ bm

SG B:

btu/lbmf, btu/:bm

sc c: ________psia

b. Calculate SG Exit Steams Enzhalpies

Sr.En-halvY wc. nrhaipy sXIc Enthalny

"0.0) ntu/lbm

SG A: i..DO x 4 x _____

4

5C B: 1.00 X

0 .00 x ____

+

SG C: 1.00 x

2. Feedwatet EnzhaloY (Stm Tables LockuP)

FW Enthal-py (hjQ

-v _ -A, _ I I -, _ _

?W, Entn& ~p A Enthalpy

A-'-

£x~r 'Enzhalpy

SCTA: sru; Ibm

Page 18of 2I

JPM COM-A. 1-2

HARRIS

ATTACHMENT FOR JPM COM-A1-2

(TO BE COMPLETED AND RETURNED TO EXAMINER)

Attachment 5

Sheet 2 of 2

Calorimetric worksheet

4. steam Generator Powers

FW Flow A Enthalpy Qf;

yMzý/r

MPPH) jbtu/lbm)

2 A

Mbru/ hr

X

Mh-u/ hr

x

5. Calciu!ate Total Reactor Power

- 42.31 m.hu/hr

Q.--. 2>ý

Q;ýiA

6. convert Mbtu-/hr to MW:,

Mbtli/hr 3.4121 Mbtu/hr/MW: M.W.,

7. Calculate Percent of Rated Thermal Power

MWV' x !00  % RTP

2900 MWY-.

8. 2ower Ranqge N Surveillance

Highest PR N: t: Cal' d Power ý%i

S

Calc':i Power A%]

Lowest PR N:.(%x

-erformed By:

Verifed By:

Page 19 of 21

JPM COM-A. I-2

HARRIS

ATTACHMENT FOR JPM COM-A1-2

(TO BE COMPLETED AND RETURNED TO EXAMINER)

Attiachment '

Sheet I of 1

Cerýifications and Reviews

a: Periodic Surveillance Requirement:

This OST was performed as

post Maintenance operability Test: ....

Redundant Subsystem Test:

Mo d e : -

Plant Conditions:

Date:

OST Completed By:

Time: ___

OST Performed By:

Name ýPrint) init ialis Name (Print)

initials

BJ Bob Jones

SS Samuel Snead

Actions/Exceptions:

General Comnmenlts/Recommendations/Correcnive

Pages Used:

OST Completed with NO EXCEPTIONS / EXCZPTICNS:

Unit SCQ

this 0S, becomes1/2 a QA R a'1*

After receiving the final rev-ew siqnature,

shouldci b~s subn~i;: 2t ed to DoCuLment Services.

Page 20 of 21

JPM COM-A. 1-2

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is operating at approximately 100% power. ERFIS is out-of-service and is

expected to be out for an extended period of time.

OST-1204, Power Range Heat Balance, Manual Calculation, Daily Interval, Mode I

(Above 15% Power) is to be performed to meet the periodic surveillance requirement

for Technical Specification 4.3.1.1, Table 4.3-1, Item 2a.

Steam Generator Blowdown is isolated.

I&C Technicians have collected all necessary data for the calculation.

INITIATING CUE(S):

You have been directed to perform OST- 1204, Power Range Heat Balance, Manual

Calculation, Daily Interval, Mode I (Above 15% Power), by completing Attachment

5, "Calorimetric Worksheet," and Attachment 6, "Certifications and Reviews."

NOTE: The Examiner will provide you with completed Attachments 1-4 and copies

of Attachments 5 and 6 for you to complete.

Page 21 of 21

JPM COM-A.2

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM COM-A.2

Review an Equipment Clearance

S

3X)D

9 Dflft C7 --

CANDIDATE:

EXAMINER:

Page I of 9

JPM COM-A.2

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Review an Equipment Clearance

ALTERNATE PATH: None

FACILITY JPM NUMBER: IP-164 (Modified)

KA: 2.2.13 IMPORTANCE: SRO 3.8 RO 3.6

KA STATEMENT: Knowledge of clearing and tagging prrocedures.

- a

TASK STANDARD: Identifies-both discrepancies on clear ance 40A.pn,4c

SIMULATOR IN PLANT

PREFERRED EVALUATION LOCATION:

PERFORM SIMULATE

PREFERRED EVALUATION METHOD:

REFERENCES: * OPS-NGGC-1301, Equipment Clearance

SS-1311, Simplified Flow Diagram Boron Recycle System

  • CWD2166B-401

VALIDATION TIME: 30 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 9

JPM COM-A.2

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

  • Provide candidate with Attachment which is the completed clearance form
  • OPS-NGGC-1301, "Equipment Clearance"
  • S-1311, "Simplified Flow Diagram Boron Recycle System"
  • CWD 2166B-401

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

I

room steps shall be performed for this JPM, including any required communications.

or asked by

will provide initiating cues and reports on other actions when directed

indicate

you. Ensure you indicate to me when you understand your assigned task. To

I provide you.

that you have completed your assigned task, return the handout sheet

INITIAL CONDITIONS:

The unit is operating at 30% power.

The internals for 3BR-153, Recycle Evaporator Feed Pump 1&2B Discharge Check

and

Valve, must be replaced. Recycle Evaporator Feed Pump 1&2B has been secured

Pump I&2A is aligned for operation.

been

Mechanical Maintenance has submitted a clearance request. The clearance has

manually generated.

INITIATING CUE(S):

You are to review the Equipment Clearance Tag Sheet for 3 BR- 153 and identify

EVERY discrepancy.

review

NOTE: Individual tags have NOT been generated and are NOT part of the

process.

Page 3 of 9

. JPM COM-A.2

HARRIS

START TIME:

  • DENOTES CRITICAL STEP

JPM PROC SAT/

ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

I NA Obtains procedure and Obtains current copy of

required information NGGC-1301, S-1311,

and OP-109

NOTE: JPM IS WRITTEN FOLLOWING THE

GUIDELINES OF NGGC-1301, STEPS 9.2.1.10,

9.2.1.13, and 9.2.1.25. NO SPECIFIC ORDER FOR

PERFORMANCE OF THE JPM IS REQUIRED

PROVIDED THE CANDIDATE IDENTIFIES THE

DISCREPANCIES. JPM STEPS ARE WRITTEN IN

THE GENERAL FLOWPATH THAT THE PUMP

MUST BE TAGGED FIRST, FOLLOWED BY

DISCHARGE PATH, SUCTION PATH, AND THEN

DRAINS AND VENTS.

Determines that

2 19.2.1.1 O.a I For systems where a pump or clearance correctly has

fan is affected by the

clearance, the clearance pump secured (initial

should be installed in the conditions) and control

following sequence to prevent switches have info tag

damage to equipment: hung before tagging

  • Secure pump/fan and power to pump

hang a tag on its control

switch.

  • 3 9.2.1.10.b Remove the power source Determines that Critical to

breaker for pump is determine that

for the pump/fan prime sequence for

mover (open breaker, tagged out of sequence

as it is to be tagged tagging pump

remove fuse, shut steam breaker is not

supply valve and so forth) prior to closing any

valves correct to ensure

and place tag on the power

pump protection.

source.

Reposition valves from Determines that

4- - 9.2.1.10.c clearance correctly does

control switches, as required

by the clearance, and place not identify any motor

tags on the control switches. operated valves

Include tags for switches in requiring tagging

alternate locations if

applicable. II

Page 4 of 9

JPM COM-A.2

HARRIS

JPM PROC SAT!

ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

.1_______________________________________________ ____________________

I Remove power source Determines that

5 9.2.1.1O.d

(electrical, air, hydraulic, and clearance correctly does

so forth) from valves, if not identify any motor

applicable, and tag the power operated valves

source removed. requiring tagging

  • 6 I 9.2.1.10.e Reposition manual valves as "7 Determines that Critical to isolate

discharge valve is all boundary

required by the clearance isolations.

and place tag on correctly tagged

handwheels of the valves prior to suction

covered by the clearance. valve, but

For pumps, shut the incorrectly tagged

discharge valve before prior to pump

shutting the suction valve. breaker being tagged

(noted previously in

JPM Step 3)

"* Determines that

3BR-157, REFP

1&2B Recirc

Return to RHT

Isol, is NOT

included on

clearance, but

should be included

7 19.2.1.13 For devices having a remote Determines that all

operator, such as a valve valves on clearance that

have reach rods have

reach rod, where both valve

and reach rod have a clearances hung

handwheel and are accessible, correctly on both the

the clearance should be valve handwheel and the

reach rod

written such that both

mechanical devices are

tagged.

8 9.2.1.25 Whenever possible, an Determines that drain

atmospheric drain and/or vent and vent paths are

between the work area and included as part of

sources of pressure to the clearance

work area should be tagged in

the open position with the

cap/flange removed to release

pressure in systems and to

accommodate thermal

I I expansion and contraction. II

Page 5 of 9

JPM COM-A.2

HARRIS

ELEMENT STANDARD NOTES SAT /

JPM PROC

STEP STEP UNSAT

9 Inform clearance preparer of Informs clearance

discrepancies preparer of 2

discrepancies

"* Incorrect order of

discharge valve /

pump breaker

"* Missing boundary

isolation valve

TASK COMPLETE

STOP TIME:

Page 6 of 9

JPM COM-A.2

HARRIS

ATTACHMENT 3

Sheet 1 of 1

Operations Clearance Form

Clearance No. 02-99001

System No ....... .......

10 Operations Approval 3BR-153, Recycle EvaporatorFeed Pump 1&2B DischargeCheck Valve

1.1 Principal Equipment --------------------------------------------------------------------------

Date I Time

1.2

Prepared-By(Planned-----------------

6y Date / Time

De;iiied

1.3

per Checklist and required documents hsted in 2.1 have

1. Authoritation to hang: Equipment may be removed from service

been activated.

Yes/No

2.1 Tech Spec/ESF/Fire Protection System operability affected?

Required Documents:...............

Date I Time

as requested)

3.0 Checklist completed. (Clearance Checklist completed

Date I Time

Signature

Clearance Ac.cented: 5.0 Clearance

Equipment Released:

ready to be operated or remark made

Indiviual signing has verified clearance establishes in the Special Instructions as to why not.

adeguate boundary. I Signature DatleTime Grounds

must sign Step 5.0 before clearance is canceled.

6.0 Authorization to Cancel: The individuals signing Step 4.0

Restored Position and Order to be Restored

6.1 All work completed Ground removal authorized. sections prepared.

Date 'Time

Signature

Signature Date f Time

Checklist.

62 Authorized to lift. Equipment may be restored to service per

Date : Time

Di-stributed by SRO

6.3 Checklist completed. (Clearance Checklist completed as requested)

Date , Time

7.0 Review - Equipment Realigned as Required" Yes / NA OP VIE LIU Updated? Y

Clearance Removed from required documents? I

Date / Tire

3BR-158 - recordnumber of turns open when closing

Special Instructions/Refereflces

Page 7 of 9

JPM COM-A.2

HARRIS

ATTACHMENT 4

Sheet I of 1

Operations Clearance Checklist

Clearance No. 02-99001

Page _ of /

a

Change (Circle one)

Checklist TypeQLift; Boundary

INT NAME (PRINT)

INT NAME (PRINT)

-- -- - - ---------

IfNO. NIA the Blocks

  • Independent Verification RetuiredQ<D2

Completed.

osition Equipment/Component By IV By

Seq Action Type Tag ld P

STOP BR EVAP FEED PMP B CS

1 HANG CIT WPS PnI

'ORMAUJ BR EVAP FEED PMP B

I HANG CIT CS-3587.1 N STOP

'-I-

SHUT REFP 1&2B Discharge lsol Valve

HANG RED 3BR-158 (A'507, EL 243)

2

REFPIA2B DischargeIsol Valve

SHUT

HANG RED 3BR-158 Reach Rod (A507, EL 2439

2

OFF Recycle Evap Feed Pump I&2B Bkr

3 HANG RED 1-4Bll-41

SHUT

REFP1&2B Suction Isol Valve

4 HANG RED 3BR-147 (A4506, EL 2381)

SHUT

REFP I&28 Suction Isol Valve

4 HANG RED 3BR-147 Reach Rod (A0506, EL 238')

REFP I&B DischargeHeader

OPEN

HANG RED 3BR-154 Inner Drain Isol (A506, EL 239)

5

REFP 1&2B DischargeHeader

OPEN

HANG RED 3BR-155 Outer Drain Isol (A,506, EL 238)

5

SBR-150 REFP I&2B Casing DrainInner Isol

RED OPEN

5 HANG Valve (A510, EL 2379

5 HANG RED 3BR-I50 REFP I&2BR CasingDrain Inner Isol

OPEN Valve Reach Rod (A510, EL 237))

5 HANG RED 3BR-151 REFP 1&28 Casing Drain Outer Isol

OPEN

Valve (A510, EL 237)

5 HANG RED 3BR-151 OPEN REFP I&2 Casing Drain Outer /sol

Valve Reach Rod (A510, EL 2379

5 HANG RED 3BR-148 REFP I&2B StrainerInlet Press Px

OPEN

(A506, EL 237)

Continued YO

Page 8 of 9

JPM COM-A.2

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The unit is operating at 30% power.

The internals for 3BR- 153, Recycle Evaporator Feed Pump 1&2B Discharge Check

Valve, must be replaced. Recycle Evaporator Feed Pump l&2B has been secured and

Pump 1&2A is aligned for operation.

Mechanical Maintenance has submitted a clearance request. The clearance has been

manually generated.

INITIATING CUE(S):

You are to review the Equipment Clearance Tag Sheet for 3BR- 153 and identify

EVERY discrepancy.

NOTE: Individual tags have NOT been generated and are NOT part of the review

process.

Page 9 of 9

9.2.1 Administrative (Cont.)

10. For systems where a pump or fan is affected by the

clearance, the clearance should be installed in the following

sequence to prevent damage to equipment:

a. Secure pump/fan and hang a tag on its control switch.

b. Remove the power source for the pump/fan prime

mover (open breaker, remove fuse, shut steam

supply valve and so forth) and place tag on the power

source.

c. Reposition valves from control switches, as required

by the clearance, and place tags on the control

switches. Include tags for switches in alternate

locations if applicable.

d. Remove power source (electrical, air, hydraulic, and

so forth) from valves, if applicable, and tag the power

source removed.

e. Reposition manual valves as required by the

clearance and place tag on handwheels of the valves

covered by the clearance. For pumps, shut the

discharge valve before shutting the suction valve.

f. Deviations from the above sequence are allowed for

safety, ALARA, or the deviation would not impact

personnel or equipment safety.

11. Components operated from a control switch should have a

Clearance Information Tag placed on the control switch if

the switch does not form a part of the clearance boundary.

For switches that are a part of the clearance boundary, a

miniature clearance tag or a switch cap that will not obscure

other switches or indications should be used.

12. For clearances that involve the removal of fuses, fuse

control and accountability shall be according to site

procedures.

01Rev.

OPSNGG-1 9 Page 28 of 76

CONTACTS

IAI --- IA22 A

I B -II- IB2

SPRING RETURN TO NORMAL

X-CONTACT CLOSED

XTHIS SHEET

-CONTACT

THIS SHEET CLOSED

SS-358T

CONTACTS

.-- - I 2 1-2

3*--4 3-4

5--1"-6 5-6

"8

1.--- 7T-8

MAINTAINED

X -CONTACT CLOSED

w THIS SHEET

NOTESs

I. CONTACT OPENS ON LOW LEVEL

IN RECYCLE HOLDUP TANK

Y041-0 LOWAL St

I (ý,I 5 AL _ I CONTROL

OUTPUT 11-2 L0C NO 2. INPUT

FOR TO WPAC-103

RECYCLE HOLDUP TANK LEVEL (S

SEE SH36II

COMPUTER

oo.,TB-I

(1364-22783)

jANN

I A1

(34278

NOTE 2 IALB-IOI (SH4331)

CA$ ALC-

(1364-34998;2

J

d

ORIGINALLL SI*EDR IiJ)LALED OWING

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

-I

NOSIASIStill MI01Id~N

a

L20

IS,

t I ' mm

JPM RO-A.3

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM RO-A.3

Establish

Perform Licensed Operator Actions to

a Liquid Waste Release

CANDIDATE:

EXAMINER:

Page I of 7

JPM RO-A.3

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

Release

TASK: Perform Licensed Operator Actions to Establish a Liquid Waste

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

IMPORTANCE: SRO NA RO 4.4

KA: 2.3.11

KA STATEMENT: Ability to control radiation releases

TASK STANDARD: Determines release rate is at or less than 80% of the

Maximum Effluent Flow Rate on release permit.

SIMULATOR IN PLANT

PREFERRED EVALUATION LOCATION:

_

PERFORM SIMULATE

PREFERRED EVALUATION METHOD:

REFERENCES: OP-120.06.02, Waste Evaporator Condensate Tanks

OP-141, Cooling Tower and Reservoir Complex

OP-I 18, Radiation Monitoring System

MINUTES TIME CRITICAL: No

VALIDATION TIME: 10

CANDIDATE:

FINISH TIME:

START TIME:

MINUTES

PERFORMANCE TIME:

SAT UNSAT

PERFORMANCE RATING:

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 7

JPM RO-A.3

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

in

  • Ensure CLG TWR MU BYP CHAN SEL in 'B' and SETPOINT SELECTOR

'LOW'.

  • Adjust CS-1908 to establish flow at approximately 7,000 gpm.
  • Select 'GRID 1' on RM-11.

OP-120.06.02, "Waste Evaporator Condensate Tanks"

OP-141, "Cooling Tower and Reservoir Complex"

OP- 118, "Radiation Monitoring System"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

performed. All control

I will explain the initial conditions and state the task to be

communications. I

room steps shall be performed for this JPM, including any required

directed or asked by

will provide initiating cues and reports on other actions when

task. To indicate

you. Ensure you indicate to me when you understand your assigned

sheet I provide you.

that you have completed your assigned task, return the handout

INITIAL CONDITIONS:

for discharge in

Waste Evaporator Condensate Tank 1&2A is being aligned

Tanks."

accordance with OP-120.06.02, "Waste Evaporator Condensate

INITIATING CUE(S):

performing the

You have been directed to coordinate with the Rad Waste Operator

discharge to complete any actions required in the Control Room.

Page 3 of 7

JPMHARRIS

RO-A.3

START TIME:

  • DENOTES CRITICAL STEP

ELEMENT STANDARD NOTES SAT /

JPM PROC UNSAT

STEP STEP

Obtains current copy of May not obtain

I NA Obtains procedure OP-120-06.02, OP-141, copy of OP-

and OP- 118 120.06.02

Rad Waste since

Operator

provides

instructions on

actions to be

taken.

N9OTE: PROCEDURE STEPS LISTED ON THIS

JPM IDENTIFY ONLY THOSE STEPS THAT

WOULD BE PERFORMED IN THE CONTROL

ROOM DURING A TANK RELEASE.

OP CUE: RADWASTE OPERATOR REQUESTS

Ct) 120.06.02, THAT YOU ADJUST THE COOLING TOWER

5.2.2.6 TOTAL DILUTION FLOW RATE FOR THE

FOLLOWING:

"* REQUESTED DISCHARGE FLOW RATE OF>

12,000 GPM

"* DISCHARGE VALVE TRIP OF 11,000 GPM

  • CHANNEL'A' l1O0,13
  • SETPOINT 'HIGH'

Inn IAI D.,,o,* leL .C. TWR MIU Places switches in the Critical to

' 5.3.2.1 BYP CHAN SEL switch following positions: establish

and the SETPOINT * CLG TWR MU automatic trip

SELECTOR BYP CHAN SEL - function at proper

switch in the positions for A setpoint to

the low flow setpoint * SETPOINT terminate release

required by SELECTOR - in the event of

Radwaste Control Room HIGH low dilution flow.

Adjust 1MP-76 (FCV-1968), Adjusts 1MP-76 until Critical to

5.3.2.2 CTMU/BD X-tie Flow flow indicated on FI- establish proper

Control

total to establish

Valve,blowdown 1968A and> FI-1968B dilution flow for

required indicates 12,000 gpm release.

flow as indicated on FI

1968A & FI-1968B

Page 4 of 7

JPMHARRIS

RO-A.3

STANDARD NOTES SAT /

JPM PROC ELEMENT

STEP UNSAT

STEP

4 OP-141, Inform Radwaste Control Informs Radwaste

5.3.2.3 Room that CTMU/Blowdown Operator

Crosstie flow is in service

V OP CUE: RADWASTE OPERATOR REQUESTS THE

120.06.02, OPERABILITY STATUS OF THE WMT AND .,-

WECT FLOW INSTRUMENT LOOP FT-6119

6 5.2.2.12

(TRANSMITTER AND RECORDER).

5 Determine the operability * Determines FT-6119

status of FT-6119 transmitter is operable by no

and recorder OWPs associated 0

with FT-6119

0 Informs Radwaste

Operator

OP CUE: RADWASTE OPERATOR REQUESTS THE

120.06.02, OPERABILITY STATUS OF THE COOLING

5.2.2.213 TOWER DISCHARGE FLOW INSTRUMENT FI

1968A OR FI-1968B.

Determine the operability * Determines F1

status of Fl-1968A & Fl- 1968A & FI-1968B

1968B are operable by

proper indication

and no OWPs

associated with Fl

1968A & FI-1968B

Informs Radwaste

Operator

OP- CUE: RADWASTE OPERATOR REQUESTS A

120.06.02, LICENSED OPERATOR TO PERFORM

5.2.2.29 INDEPENDENT VERIFICATION THAT TE HK

6119, FD WST MOr&TK NVIRON FLOW

CONTROLLERMS A SS THAN 80% OF

"MAX EFFLUENT FLOW RATE" OF 35 GPM PER

At the RM-t1, select Waste Selects "Grid 4" or Critical to permit

Processing Building grid "Grid 6" reading process

6.1.2.2.a

flow for correct

channel.

Page 5 of 7

JPMHARRIS

RO-A.3

STANDARD NOTES SAT/

JPM PROC ELEMENT UNSAT

STEP STEP

  • 8 Select channel 4676 by Critical

reading to permit

process

OP-118, Select channel 4676

entering "4676" on flow for correct

6.1.2.3.b

keypad and pressing channel.

"SEL" Critical to permit

  • 9 OP-I 18, Select a trend display for Select any trend reading process

6.1.2.3.d channel 4676 display by pressing any flow for correct

one of the following: channel.

(4)

"* TREND 10 MIN

"* TREND HOURLY

"* TREND DAILY

CUE: WHEN "PROCESS FLOW NORMAL"

VALUE READ IN FOLLOWING STEP, PROVIDE

INFORMATION THAT VALUE INDICATED IS

,Qp

10 Read Process Flow Normal Determines Process

value to determine value Flow Normal value

within limits is within 25

indicates gpm which

limit of 28 gpm

(80% of max effluent

flow rate of 35 gpm)

I1 Sign verification of flow Authorizes telecom

within limits signature to be used

TASK COMPLETE

STOP TIME:

Page 6 of 7

JPM RO-A.3

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Waste Evaporator Condensate Tank I&2A is being aligned for discharge in

accordance with OP-120.06.02, "Waste Evaporator Condensate Tanks."

INITIATING CUE(S):

You have been directed to coordinate with the Rad Waste Operator performing the

discharge to complete any actions required in the Control Room.

Page 7 of 7

5.3 Startup of CTMU/Blowdown Crosstie System

5.3.1 Initial Conditions

1. CTMU in service per section 5.1 or section 8.1.

5.3.2 Procedural Steps

CAUTION

must maintain

There is no indication of actual CTMU Pump flow. Operators

of flow requirements placed on CTMU Pumps. Starting a

an awareness

than

second CTMU Pump when running pump discharge pressure is less

35 psig will prevent pump runout.

as CTMU Pump

Proper operation of 3MP-11, Recirc Vlv, should be verified

flow is varied, to ensure CTMU Pump minimum flow requirements are met.

from

CTMU flow to the basin on FI-1960A and Cooling Tower Bypass flow

are used to control 3MP-11 in AUTO. Other flow requirements on

FT-1968A

open in AUTO.

the CTMU Pump could cause CTMU Pump runout with 3MP-11

point FMPI961A,

The control signal for 3MP-11 is monitored by computer

is the total of FT-1960A, CTMU to

Total CTMU and Bypass Flow. FMP1961A Flow.

Chamber Unit 1 and FT-1968A, CTMU/BD X-Tie Total

SW Pump

SELECTOR

1. Place the CLG TWR MU BYP CHAN SEL switch and the SETPOINT by

required

switch in the positions for the low flow setpoint

Radwaste Control Room.

Channel Selector Setpoint Selector Low Flow Setpoint

A LOW 4,000

CHAN

A HI 11,000

CHAN

B LOW 7,000

CHAN

B HI 15,000

CHAN

of flow

NOTE: FI-1968A & B indicate total blowdown flow (a summation Control

through FT-1968A & B and FT-1974A & FU-1974B). Radwaste

on the WPS

Room can call up individual flow transmitter flows

computer.

windows 1-1

Only FT-1968A & B feed CTMU Control Panel annunciator greater

and 2-1. CTMU/Blowdown Crosstie flow should be maintained

alarm on

than 500 gpm and less than 15,000 gpm by absence of

2-1.

CTMU Control Panel annunciator windows 1-1 and

Valve, to

2. Adjust IMP-76 (FCV-1968), CTMU/BD X-tie Flow Control on FI-1968A &

establish total required blowdown flow as indicated

FI-1968B.

Crosstie flow is

3. Inform Radwaste Control Room that CTMU/Blowdown

in service.

Rev. 17 Page 10 of 40

OP-141

Discharging the Contents of the WECT AMB* to Cooling Tower Discharge

5.2

R (Reference 2.2.0.01.b)

5.2.1 Initial Conditions

recycled and has been

i. Waste Evaporator Condensate Tank is being

R sampled per Section 5.1 (Reference 2.5.0.01).

2. Cooling Tower Discharge is available to receive discharge.

3. No batch discharge being made from the following:

Treated Laundry and Hot Shower Tanks

Floor Drain Waste Monitor Tanks

Secondary Waste Sample Tanks

with a continuous release of

NNE: The WECT can be discharged simultaneously

the Secondary Waste Sample Tank.

5.2.2 Procedural Stens

has been sampled and

1. If the statement "The above-named source

COMPLIANCE" appears in Part V AUTHORIZATION

R analyzed but is NOT IN perform the

section of the Batch Liquid Effluent Permit,

following: (Reference 2.2.0.01.b)

make this release.

Obtain Manager - Operation permission to

that release is in

Attach supporting documentation from E&RC

compliance of 10CFR20 and IOCFR50 regulations.

release on the Batch

2. Check Tot-Body and Organ Doses from this dose from this

Liquid Effluent Release Permit. If Tot-Body

2 or any Organ dose from this release

release exceeds 5x10, mrem

8x10, 2

mrem, cancel the release per Section 7.2 and

exceeds

gives permission to

reprocess the tank UNLESS Manager - Operation

release tank above these guidelines.

number (located in

3. Record the WECT Batch Liquid Effluent Permit

on Attachment 3.

top right corner of permit)

the Batch Liquid

4. Record the "MAX. EFFLUENT FLOW RATE" from 2.4.0.02).

Effluent Permit on Attachment 3 (Reference

R

must be the same one

NOTE: The CTBD Channel and Setpoint selected

3. A value lower than the required flow

selected on Attachment

DISCH ISOLATION VLV 3FD-421

rate will trip FLR DRN WST MON TKS

shut.

flow (4,000 gpm) has

If all CTBD channels are inoperable and weir

any channel and setpoint can be

been selected for dilution qater,

that will allow ALB-106-14-6 LO CLG TWR BLDG FLOW to

selected

This will allow 3FD-421 to open. Dilution water will be

reset.

based on weir flow.

Channel and Setpoint as

5. Request the MCR to set the proper CTBD

3 (Reference 2.5.0.01).

R indicated on Attachment

Page 11 of 55

C 1 w* i+ 18

14

OP-120.06.02 Rev.

5.2.2 Procedural Steps (continued)

Flow

6. Request the MCR to adjust the Cooling Tower Total Dilution below:

and Setpoint settings as shown

Rate for the proper Channel

Requested Discharge

Flow Rate Valve Trip Channel Setpoint

3,800 A LOW

greater than 5,000

6,650 B LOW

greater than 8,000

greater than 12,000 10,450 A HIGH ..

~tKE~ 6,00 14,250 B HIGH

SHUT position

7. Verify the following valves are in the KEYLOCKED

TREATED L&HS TKS DISCE BLOCK VLV 3LHS-297

FLR DRN WST MON TKS DISCH BLOCK VLV 3FD-422

must be

SEC WST SAMPLE TK DISCH BLOCK VLV 3SWT-152 (3SWT-152

Secondary

KEYLOCKED SHUT unless a Continuous Release of the

Waste Sample Tank is in progress.)

8. Ensure shut the following valves:

>. FLOOR ORN WST MON TANK A PUMP DISCH VLV 3FD-368

%)~. FLOOR DRN WMT

3FD-408, MON TANK

WST Pump B PUMPTo DISCH

Discharge WPS WHT 3FD-403 Valve

VLV Isolation

'-Al

Tank

3FD-406, WMT Pump Discharge To Condensate Storage

"9./,If REM-3541 is OPERABLE, perform the following steps:

R (Reference 2.5.0.01)

by observing

a. Ensure the REM-3541 Sample Pump is operating

light is illuminated on Channel 4676.

FLOWING

Condensate

cA b. Perform Waste Monitor Tanks and Waste Evaporator

3541 Source Check (OP-119,

Tanks Radiation Monitor 3.

Section 8.0) and record the results on Attachment

specific response setpoint, which

NOTE: The ODCM software calculates a nuclide The setpoint equates

for each nuclide.

is based on the sum of responses

nuclides to Cs-137, to which the monitor is

all gamma-emitting and the units

calibrated. The setpoint is listed in terms of Cs-equiv

are gCi/ml.

Batch Liquid

c. Record the "MAX SETPOINT" in Cs/equiv (from

Effluent Permit) on Attachment 3.

(from Batch Liquid

d. Record the "ALERT SETPOINT" in Cs/equiv

Effluent Permit) on Attachment 3.

in Cs/equiv

e. Using Supervisor Key, enter the "MAX SETPOINT"

Liquid Effluent Permit into RM-11 Channel

from the Batch

High Alarm Limit). Record on

4676 Channel Item 9 (Channel

Attachment 3.

Rev. 18 Page 12 of 55

OP2.......

OP-12O.O6.02

5.2.2 Procedural Stens (continued)

f. Using Supervisor Key, enter the 'ALERT SETPOINT" in Cs/equiv

from the Batch Liquid Effluent Permit into RM-li Channel

4676 Channel Item 10 (Channel Alert Alarm Limit). Record on

Attachment 3.

for

g. Using Supervisor Key, perform a database verification

channel 4676 (REM-3541) as follows:

(1) Key 4676 and press SEL.

(2) Press LIT - GRID 5 - SEL.

in the RMDSL

NOTE: Monitor Items and Channel Items which are not listed

Monitoring System Data Sheet Library) are either fixed values

(Radiation

are not used at SHNPP. Monitor

which cannot be changed or values which

Items which are not listed in the RMDSL do not need to

Items and Channel

be validated in the next steps.

(3) Ensure Monitor Items I - 55 and channel items 9 - 20

for 4676 which are listed in the RMDSL match the RMDSL

Values.

(4) Key 56 and press SEL.

(5) Ensure Monitor Items 56 - 84 for 4676 match the RMDSL

values.

(6) Key -22 (minus sign and 22) and press SEL.

(7) Ensure Channel Items 22 - 24 for 4676 match the RMDSL

values.

(8) Press LIT - GRID I - GRID 4 - GRID 6 - GRID 3 - SEL.

pad:

(9) Enter the following password using the RM-11 key

2 - 4 - 0 (240) and SEL.

(10) Key 3 and SEL to access the channel items.

(11) Ensure Channel Items I and 32 match the RMDSL values.

h. If any discrepancy is found during the database

verification, contact HP.

the "MAX SETPOINT"

i. Perform an Independent Verification that

and the 'ALERT SETPOINT" from the Batch Liquid Effluent

Permit has been entered on the RM-11 Channel 4676, (Items 9

and 10). Record on Attachment 3.

-...... V . Rev. 18 Page 13 of 55

OP-120.06.0

5.2.2 Procedural Sters (continued)

steps:

10. If REM-3541 is INOPERABLE, perform the following

R a. Ensure Chemistry has completed the Confirmation of Duplicate

Sampling and Release Rate Calculations for Inoperable

form with Release

Monitor Form from CRC-854 and forwarded

Package.

Channel 4676

b. Using Supervisor Key, enter 0.00E+00 into RM-11

Channel Item 9 (High Alarm Setpoint).

RM-11 Channel 4676

c. Using Supervisor Key, enter 0.00E+00 into be 0.00

Channel Item 10 (Alert Alarm Setpoint). (Should

E1o)

FD WST MONITOR TK

ii. Record the WECT Batch Release Number on UR-6119,

TO CLG TWR BLOWDOWN FLOW, chart paper.

WMT and WECT Flow Instrument

12. Request the operability status of the Record

and recorder) from the MC/.

R Loop FT-6119 (transmitter 3

instrument operability status on Attachment

(Reference 2.5.0.01).

Cooling Tower Discharge

13. Request the operability status of the

from the MCR. Record

R Flow Instrument FI-1968A or FI-1968B 3

instrument operability status on Attachment

(Reference 2.5.0.01).

By".

14. Review Attachment 3 and sign --Requested

Tank Discharge Log

15. Take Attachment 3, Waste Evaporator Condensate to the

Radioactivity Waste Release Permit

and the Liquid and obtain proper

Superintendent - Shift Operations for approval

key to make release.

3.

16. Record the WMT/WECT "FQ-6119 Start" reading on Attachment

step may be different than WECT level

NOTE: The "Start Tank Level" in the next due to WECT discharge piping

recorded earlier for mixing calculations

flush.

17. Record the "LI-6025 A(B) "Start" in percent and gallons on

Attachment 3.

controller is set at 0%

is. Ensure HK-6119, FD WST MON TK TO ENVIRON,

so valve 3FD-414 is SHUT.

2 Rev. 18 Page 14 of 5 5

OP-120.06.0

5.2.2 Procedural Stens (continued)

and FI-1968B

19. If Cooling Tower Discharge Flow Instruments FI-1968A

are both INOPERABLE, perform these steps:

Discharge

a. Initiate OP-120.10.04 Attachment for Cooling Tower

the "Batch

Flow Instrumentation Inoperable Log, by recording

Liquid Effluent Permit Number" and the "Start Date."

b. Estimate the Total CT Discharge Dilution Flow per

Flow

OP-120.10.04 Attachment for Cooling Tower Discharge

Inoperable Log and record results in the

Instrumentation

"Pre-Release" Section.

c. Verify the Total CT Discharge Dilution Flow Pre-Release

value

value is greater than the "DILUTION FLOW AVAIL"

Permit Request Section of

recorded on the Discharge

Attachment 3.

enough

d. If the Total CT Discharge Dilution Flow is not high

request MCR to increase the Cooling

in Step 5.2.2.019.c,

Tower Discharge Rate to appropriate flow. Record new flow

on OP-120.10.04 Attachment for Cooling Tower Discharge Flow

Instrumentation Inoperable Log.

TO CLG TWR BLOWDOWN

20. Verify recorder UR-6119, FD WST MONITOR TK

and advancing properly. Record results on

FLOW, is inking

Attachment 3.

PUMP DISCH VLV 3WE-221 (3WE-247) switch to

21. Place the WECT A(B)

OPEN.

CAUTION

to the Waste Neutralization

Radioactive liquids should never be discharged

Discharge Permit is based on dilution water from Cooling Tower

System. would cause a

Blowdown. In addition, discharge to Waste Neutralization

in the Waste Neutralization Setting Basin.

buildup of contamination

switch

22. Place the FLR DRN WST MON TANKS DISCH VALVE 3FD-426/3FD-427

to the TO CLG TOWER position.

VLV 3FD-421 switch

23. Place the FLR DRN WST MON TKS DISCH ISOLATION

to OPEN.

DISCH BLOCK 3FD-422

24. Insert key and place the FLR DRN WST MON TANKS

to Keylocked OPEN.

WST MON TANKS DISCH

25. Perform independent verification that FLR DRN

switch is in the TOQ_gL TOWER position.

VALVE 3FD-426/3FD-427

WST MON TANKS DISCH

26. Perform independent verification that FLR DRN

BLOCK 3FD-422 is Keylocked OPEN.

flow path by

27. If REM-3541 is INOPERABLE, verify the discharge

Attachment 6, Waste Evaporator Condensate Tanks

R completing OWP-RM-10,

Checklist. Inform Unit SCO per

Discharge Valve Lineup

LCO Action Log Sheet. (Reference 2.5.0.01)

Rev. 18 Page 15 of 555

OP-120.06.02

5.2.2 Procedural Steps (continued)

Release

NOTE: A Licensed Operator must be able to independently verify the

This can be done locally in the RWCR or by

Flow in the next step. a

reading from a RM-11 by entering Channel 4676, depressing

obtaining

Trend Key and reading the Process Flow N.

28. Adjust setpoint on HK-6119 FD WST MON TK TO ENVIRON flow

controller until flow is at 80% of "MAX. EFFLUENT FLOW RATE"

UR-6119

specified on Attachment 3, as indicated on Flow Recorder

may be

(Computer Point FA-429, FX-433 or Flow Integrator FQI-6119

used to estimate flow if UR-6119 is INOPERABLE). Log on

Attachment 3.

29. Request a licensed Operator to perform independent verification

is at or

R that the HK-6119 FD WST MON TK TO ENVIRON flow controller

FLOW RATE" (either by observing

less than 80% of "MAX. EFFLUENT

Flow N on

HK-6119 flow locally in RWCR or by observing Process

on Attachment 3 and log on

RM-11 channel 4676) specified

Attachment 3. If flow was verified by observing RM-Il Process

per

Flow N, then licensed Operator's signature can be done

telecom. (Reference 2.4.0.02).

CAUTION

must remain a minimum

The WECT Pump A(B) Recirculation Valve 3WE-218 (3WE-244)

turn open to prevent operating the pump at shutoff head if the release

of one

trips.

30. If needed, throttle 3WE-218 (3WE-244), Waste Evaporator Condensate

Tank Pump Recirculation Valve to keep WECT Pump running while

R release

checking the flow rate to ensure flow is within proper

limits. (Valve must remain at least one turn open)

(Reference 2.4.0.03).

31. Record the "Discharge Start Date' and "Time" on Attachment 3.

32. Notify Superintendent - Shift Operations that release has started.

33. Notify HP that WECT release has started.

Tanks Flow

34. If Waste Monitor Tanks and Waste Evaporator Condensate

has not been

R instrument loop 6119 is OPERABLE and a channel check

performed this shift, perform Waste Monitor Tanks and Waste

Channel

Evaporator Condensate Tanks Discharge Flow Instrumentation

8.0) at this time. (If a channel check has already

Check (Section

of previous channel check

been performed this shift, results

not need

should be recorded on Attachment 3 and another one does

Record results on Attachment 3.

to be performed this shift.)

(Reference 2.5.0.01).

is

35. If WMT and WECT FT-6119 (Transmitter, Recorder, and Indicator)

at least once per two hours during

R INOPERABLE, estimate flow rate

release. Document estimated flow on Attachment 5, Waste

Inoperable

Evaporator Condensate Tank Discharge Flow Instrument

Log (Reference 2.5.0.01).

Rev. 18 Page 16 of 55

OP-120.06.02

5.2.2 Procedural Steps (continued)

is OPERABLE,

36. If either Cooling Tower Discharge Flow Instrument

perform this step;

Channel

a. Perform Cooling Tower Discharge Flow Instrumentation

Check (OP-120.10.04, Section 8.0). (If a channel check has

does not need

already been performed this shift, another one

Record results on Attachment 3.

to be performed.)

(Reference 2.5.0.01).

Dilution on

b. Record the current Cooling Tower Discharge Total

Attachment 3.

go

c. If CTBD Discharge Flow Instrument Channel Check passed,

to step 5.2.2.038.

INOPERABLE, perform

37. If Cooling Tower Discharge Flow Instrument is

R the following steps (Reference 2.5.0.01):

rate at least

a. Estimate the Total CT Discharge Dilution Flow

once per two hours during release.

for

b. Document estimated flow on OP-120.10.04 Attachment

Flow Instrument Inoperable Log.

Cooling Tower Discharge

Flow

c. Enter -'Inoperable, see Cooling Tower Discharge

Discharge

Estimates" on Attachment 3 in the "Cooling Tower

Total Dilution Flow Rate" blanks.

is lost as

38. During release, if Cooling Tower Dilution Flow the

indicated by ALB-106-14-6 LO CLG TWR BLDN FLOW, perform

following steps:

has

a. Ensure FLR DRN WST MON TKS DISCH ISOLATION VLV 3FD-421

SHUT.

b. Keep WECT Pump running to ensure mixing through

recirculation line.

Recirculation

c. Throttle open 3WE-218 (3WE-244) WECT Pump A(B)

Valve to ensure adequate recirculation flow.

release is

d. Record in Attachment 3 Comment Section the time

stopped.

place the FLR

e. When Cooling Tower Dilution flow is restored,

DISCH ISOLATION 3FD-421 switch to OPEN.

DRN WST MON TKS

Rev. 18 Page 17 of 555

OP-120. -n o

5.2.2 Procedural Steos (continued)

release is

f. Record in Attachment 3 Comment Section the time

restarted.

CAUTION

(3WE-244) must remain a minimum

The WECT Pump A(B)p Recirculation Valve 3WE-218 shutoff head if the release

at

of one turn open to prevent operating the pump

trips.

Recirculation

g. Throttle 3WE-218 (3WE-244) WECT Pump A(B) while checking the

R Valve as needed to keep WECT Pump running

limits.

flow rate to ensure flow is within proper release

(Valve must remain at least one turn open)

(Reference 2.4.0.03).

Condensate Tank,

39. During the release of the Waste Evaporator

should be monitored. If REM 3541 goes into an Alert or

REM-3541

release, perform the following steps:

High Alarm condition during

should

a. If the monitor goes into alert alarm, operator to increase.

observe the reading to see if it is continuing

limit, proceed to

If it continues to approach the High Alarm

Step 5.2.2.039.b.

a High Alarm

b. If the monitor approaches or goes into

condition, perform the following steps:

VLV

(1) Ensure the FLR DRN WST MON TKS DISCH ISOLATION

3FD-421 is SHUT.

must be initiated before discharging

NOTE: A new Batch Liquid Effluent Permit

the remaining contents of the Waste Evaporator Condensate Tank.

switch

(2) Place the WECT A(B) DISCH VLV 3WE-221 (3WE-247)

to SHUT.

WST MON TK

(3) Adjust the setpoint for HK-6119 on the FD

TO ENVIRONMENT flow controller to 0%.

Evaporator

(4) Throttle open 3WE-218 (3WE-244), Waste

Condensate Pump Recirculation Valve as needed to

pressure and adequate

obtain proper pump discharge

recirculation flow.

that the

(5) Notify the Superintendent - Shift Operations

WECT Release has terminated due to REM-3541

approaching or went into high alarm.

of the

(6) Request Health Physics to verify the validity

alarm.

2 Rev. 18 Page 18 of 5! 5

OP-120.06.0

5.2.2 Procedural Steps (continued)

NOTE: If the RMS Technician determines REM-3541 is not operating as expected,

the recommendation will be made to the Main Control Room to declare

REM-3541 INOPERABLE.

(7) If the Radiation Monitor alarm is determined to be

valid, perform the following:

I Open lDW-709, WECT/WMT REM-3541 Disch Line DW

Flush/Rinse Vlv.

2 Open IIA-2063-I5, Instrument Air supply to

3DW-52, Flr Drn REM-3541 Rinse Hdr Demin Wtr Vlv

and shut drain pot.

3 Place the FLR DRN DEMIN WTR RINSE/FLUSH VALVE

3DW-52/3FD-420 switch to FLUSH. Allow to flush

for 30 seconds.

4 After 30 second flush, place the FLR DRN DEMIN

WTR RINSE/FLUSH VALVE 3DW-52/3FD-420 switch to

ISOLATE.

5 Shut IDW-709, WECT/WMT REM-3541 Disch Line DW

Flush/Rinse Vlv.

6 Shut IIA-2063-I5, Instrument Air supply to

3DW-52, Flr Drn REM-3541 Rinse Hdr Demin Wtr Vlv

and open drain pot.

7 Initiate a CR per CAP-NGGC-0001.

40. Go to Section 7.1 to shutdown the WECT A(B) Release.

Rev. 18 Page 19 of 55

OP-120.06.02

JPM RO-A.3

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Waste Evaporator Condensate Tank 1&2A is being aligned for discharge in

accordance with OP-120.06.02, "Waste Evaporator Condensate Tanks."

INITIATING CUE(S):

You have been directed to coordinate with the Rad Waste Operator performing the

discharge to complete any actions required in the Control Room.

Page 7 of 7

JPM SRO-A.3

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM SRO-A.3

Radiological Controls

CANDIDATE:

EXAMINER:

Page I of 8

JPM SRO-A.3

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Radiological Controls

ALTERNATE PATH: NA - Questions

NA - Questions

FACILITY JPM NUMBER:

IMPORTANCE: SRO 1)3.1 RO NA

KA: 1) 2.3.6

2) 2.3.4 2)3.1

KA STATEMENT: 1) Knowledge of the requirements for reviewing and

approving release permits

2) Knowledge of radiation exposure limits and

contamination control, including permissible levels in

excess of those authorized

TASK STANDARD: NA - Questions

SIMULATOR IN PLANT

PREFERRED EVALUATION LOCATION: SIMULATE

PERFORM

PREFERRED EVALUATION METHOD:

REFERENCES: OP-120.06.02, Waste Evaporator Condensate Tanks

Offsite Dose Calculation Manual

PEP-330, Radiological Consequences

15 MINUTES TIME CRITICAL: No

VALIDATION TIME:

CANDIDATE:

START TIME: FINISH TIME:

UNSAT

PERFORMANCE RATING: SAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

JPM SRO-A.3

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

OP- 120.06.02, "Waste Evaporator Condensate Tanks"

Offsite Dose Calculation Manual

PEP-330, "Radiological Consequences"

OWP-RM, "Radiation, Effluent, and Explosive Gas Monitoring"

Page 3 of 8

JPM SRO-A.3

HARRIS

START TIME:

EXAMINER'S ANSWER KEY

QUESTION #1

Tank

Radwaste is making preparations to discharge the Waste Evaporator Condensateis

/ WECT Discharge Flow,

(WECT) when it is determined that FT-6119, WMT

inoperable.

allow the WECT to be discharged

What are the license requirements that must be met to

with FT-6119 inoperable?

ANSWER:

Table 3.3

ODCM 3/4.3.3.10, Radioactive Liquid Effluent Monitoring Instrumentation,

once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

12, Action 38 requires that the flow rate be estimated at least

by referencing OWP

during the actual release (information can also be determined

RM-14)

once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during

OP-120.06.02 requires that the flow rate be estimated at least

on Attachment 5, Waste

the actual release and that the estimated flow be documented

Inoperable Log

Evaporator Condensate Tank Discharge Flow Instrument

(Required response underlined and bolded)

REFERENCES:

OP-120.06.02, "Waste Evaporator Condensate Tanks"

OWP-RM, "Radiation, Effluent, and Explosive Gas Monitoring"

Offsite Dose Calculation Manual

KA / IMP / STATEMENT:

and approving release

2.3.6 / SRO 3.1 / Knowledge of the requirements for reviewing

permits

STOP TIME:

Page 4 of 8

JPM SRO-A.3

HARRIS

START TIME:

EXAMINER'S ANSWER KEY

QUESTION #2

operations

The plant experienced a loss of coolant accident and cold leg recirculation

Recirculation." Prior to the

were established per EOP EPP-010, "Transfer to Cold Leg

bearing. RHR

accident RHR Pump lB-SB had been out-of-service due to a damaged

Pump IA-SA has just failed.

1A-SA room. HP

An emergency entry for repairs is to be made into the RHR Pump

20 Rem/hour.

reports general area radiation levels in the room are approximately

90 minutes to

Maintenance estimates that it will take a 3-person team approximately

make the necessary repairs.

that are available on site

The Maintenance Manager has supplied a list of 5 personnel

and qualified to perform the repairs. The 5 persons are:

is not pregnant, she

1) Anita Andrews is a 47-year-old married female, states she

of the radiological risks

has volunteered to make the entry, and she is fully aware

last 9 as a member

involved. She has worked at the Harris plant for 22 years, the

of the Maintenance department.

the entry,

2) Bob Ballew is a 32-year-old married male, he has volunteered to make at the

has worked

and he is fully aware of the radiological risks involved. He

since he left another

Harris plant as a member of the Maintenance department

nuclear utility 3 years ago.

he has not volunteered

3) Charles Cotton is a 51-year-old single male and although

involved. He is the

to make the entry, he is fully aware of the radiological risks

of the Maintenance

most knowledgeable of the 5 persons, having been a member

department for his entire 28 years at the Harris plant.

to make the

4) David Deaver is a 37-year-old married male, he has volunteered has worked at

He

entry, and he is fully aware of the radiological risks involved.

of the Maintenance

the Harris plant for 15 years, the last 1I years as a member

department since he left Operations.

volunteered to make the

5) Frank Furstenburg is a 56-year-old single male, he has

Although he has

entry, and he is fully aware of the radiological risks involved.

spent in the

only worked at Harris for the past 2 years, both years were

situations, having made

Maintenance department, and he has experience in these

a similar entry 17 years ago at another nuclear utility.

the emergency entry, AND why

Which 3 of these 5 persons should be selected to make

should these 3 be picked?

Page 5 of 8

JPM SRO-A.3

HARRIS

ANSWER:

Anita Andrews. Bob Ballew, and David Deaver should be selected to make this

entry. In events where exposure levels exceeding 25 TEDE would be required all

a full

personnel must be volunteers (eliminating Charles Cotton), they should have

awareness of the risks involved (all meet this requirement), and exposure under these

conditions should be limited to once in a lifetime (eliminating Fred Furstenburg).

only be

Although it is preferable to use personnel over the age of 45, age should

if they

considered where all other factors are equal. Females should not be considered

are declared pregnant, which Anita Andrews has not done.

(Required response underlined and bolded)

REFERENCES:

PEP-330, "Radiological Consequences"

KA / IMP / STATEMENT:

2.3.4 / SRO 3.1 / Knowledge of radiation exposure limits and contamination control,

including permissible levels in excess of those authorized

STOP TIME:

Page 6 of 8

JPM SRO-A.3

HARRIS

CANDIDATE QUESTION SHEET

QUESTION #2

(TO BE RETURNED TO EXAMINER UPON COMPLETION)

operations

The plant experienced a loss of coolant accident and cold leg recirculation

Recirculation." Prior to the

were established per EOP EPP-010, "Transfer to Cold Leg

a damaged bearing. RHR

accident RHR Pump 1B-SB had been out-of-service due to

Pump IA-SA has just failed.

Pump IA-SA room. HP

An emergency entry for repairs is to be made into the RHR

approximately 20 Rem/hour.

reports general area radiation levels in the room are

approximately 90 minutes to

Maintenance estimates that it will take a 3-person team

make the necessary repairs.

that are available on site and

The Maintenance Manager has supplied a list of 5 personnel

qualified to perform the repairs. The 5 persons are:

she is not pregnant, she has

1) Anita Andrews is a 47-year-old married female, states

the radiological risks

volunteered to make the entry, and she is fully aware of

the last 9 as a member

involved. She has worked at the Harris plant for 22 years,

of the Maintenance department.

to make the entry,

2) Bob Ballew is a 32-year-old married male, he has volunteered

has worked at the

and he is fully aware of the radiological risks involved. He

since he left another

Harris plant as a member of the Maintenance department

nuclear utility 3 years ago.

he has not volunteered

3) Charles Cotton is a 51-year-old single male and although

involved. He is the

to make the entry, he is fully aware of the radiological risks

of the Maintenance

most knowledgeable of the 5 persons, having been a member

department for his entire 28 years at the Harris plant.

to make the

4) David Deaver is a 37-year-old married male, he has volunteered

He has worked at

entry, and he is fully aware of the radiological risks involved.

of the Maintenance

the Harris plant for 15 years, the last 11 years as a member

department since he left Operations.

volunteered to make the

5) Frank Furstenburg is a 56-year-old single male, he has

Although he has

entry, and he is fully aware of the radiological risks involved.

were spent in the

only worked at Harris for the past 2 years, both years

situations, having made a

Maintenance department, and he has experience in these

similar entry 17 years ago at another nuclear utility.

the emergency entry, AND why

Which 3 of these 5 persons should be selected to make

should these 3 be picked?

Page 7 of 8

JPM SRO-A.3

HARRIS

CANDIDATE QUESTION SHEET

QUESTION #1

(TO BE RETURNED TO EXAMINER UPON COMPLETION)

Tank

Radwaste is making preparations to discharge the Waste Evaporator Condensate

Flow, is

(WECT) when it is determined that FT-6119, WMT / WECT Discharge

inoperable.

the WECT to be discharged

What are the license requirements that must be met to allow

with FT-6119 inoperable?

Page 8 of 8

OWP-RM-14

Sheet I of 3

WR/JO Number:

OWP - RM-14 Clearance Number:

1.

2. system: Radiation, Effluent. and Explosive Gas Monitoring

3. Component: Liquid Effluent Flow Monitors

Monitor (circle one)

4. Scope of Work: Maintenance on Liquid Effluent Flow FT-*lWL-6193

TL & HS Tank Pump to CT Blowdown (TL&ES)

(WMT/WECT) FT-21WL-6119

Waste Monitor Tk Pumps Disch ET-21WS-8513

S.W. Sample Tank Pumps Discharge (SWST)

Flow (CT Bypass) FT-OIMP-1968A/B

CTMU/BD X-Tie Total 74

B

Cooling Tower Weir Flow (CT Blowdown) FT-0lMD-l974A/FU-01MD-19

D.I. Operational

5. Applicable Requirement: ODCM, Apoendix D, Section

Requirement 3.3.3.10 (At all times)

6. Precautions: Work on FT-1968A/B, FT-1974A, or FU-1974B will each affect

the Coolina Tower Makeup Panel. If a

the respective flow indicator on Liguid Release.

failed CTMU channel is selected during a Radioactive

then the release may trip due to low dilution flow indication.

2. /

7. LCO Action Log initiated on Sheet Signature Date

N/A

8. Component lineups completed. Signature Date

the component is

9. Testing required on redundant equipment while

inoperable. None

10. Testing/Action required to restore operability.

/

1. MST-10301 for FT-*IWL-6193

2. MST-10302 for FT-21WL-6119

3. MST-10307 for FT-21WS-85133

for FT-01MP-1968A/B /

4. MST-I0310/10311

3 9

5. MST-I0308/I0 0 for FT-O1MD-1974A/ /

FU-01MD-1974B

________ _____

6. OST-2044 Date

Signature

Signature Date

11. LCO Action Log completed.

N/A

12. Component lineups restored. Signature Date

13. Remarks:

Date

14. Reviewed By: Date

Unit SCO

this OWP becomes a QA RECORD and

After receiving the final review signature,

should be submitted to Document Services.

Rev. 19 Page 50 of 92

OWP-RM

OWP-RM- 14

Sheet 2 of 3

LCO Action Log

or notes

1. Person initialing verifies stated time requirements are met

reasons why not in the remarks.

Completed

LCO Action Requirements Initials Time Date

Time/Date Component Inoperable:

LCO Management Program updated.

Name of Chemistry

Technician notified:

Name of Radwaste

Control Room

Operator notified:

Estimate flow at least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per

See Sheet 3.

OP-120.01.02, OP-120.06.02, OP-120.09.03 or

OP-120.10.04

actions are only

NOTE: For Cooling Tower flow monitors, the following two

They may be

required if both trains of monitoring are inoperable.

marked N/A if only one channel is inoperable.

Exert best effort to return the instrument to

OPERABLE status within 30 days.

If not restored to OPERABLE status within 30 days,

initiate a CR that an explanation in the next

Radioactive Effluent Release Report is required

pursuant to ODCM, Appendix F, Section F.2 of why

this inoperability was not corrected in a timely

manner.

Time/Date Operable:

LCO Management Program updated.

Name of Chemistry

Technician notified:

Name of Radwaste

Control Room

Operator notified:

Remarks:

Rev. 19 Page 51 of 92

OWP-RM

OWP-RM-14

Sheet 3 of 3

Page - of

LCO Action Log

1. Person initialing for OPS verifies that flow is estimated at least every

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or notes reasons why not in the remarks (OP-120.01.02,

OP-120.06.02, OP-120.09.03, or OP-120.l0.04) . This verification may be

done per telecon.

2. If necessary, multiple copies of this page may be used.

Time/Date Component Inoperable:

Completed OPS Comments

Time Date Initials

I I. I

_ I_ _ I_ I-

_ I_ I_ I

I___ _ I I

I I M

1. 4 I

I. I i

I I i

.1 I 4

I1 II

_ _ _I II

I. I4

I _ _ I I

Remarks:

OWP -RM Rev. 19 Page 52 of 92

Attachment 1

Sheet 1 of 1

Limitations for Lifesaving and Emergency Reentry/Repair Actions

1. A Declared Pregnant Woman shall not take part in these actions.

2. Internal exposure should be minimized by the use of the most appropriate

respiratory protection or ALARA practice whenever possible, and

contamination should be controlled by the use of protective clothing when

practical.

3. Emergency worker exposures during lifesaving and repair/reentry efforts

should be limited to the following:

DOSE LIMIT ACTIVITY CONDITION

(rem TEDE)

5 All All

10 Protecting valuable property Lower dose not practicable

25 Lifesaving or protection of large Lower dose not practicable

populations

>25 Lifesaving or protection of large Only on a voluntary basis to

populations persons fully aware of the risks

involved

4. Limit dose to the lens of the eye to three (3) times the above values and

doses to any other organ (including thyroid, skin and body extremities) to

ten (10) times the above values.

5. Entry into radiation fields of greater than 25 rem/hr or exposure in excess

of 5 rem TEDE shall not be permitted unless specifically authorized by the

Site Emergency Coordinator.

6. In emergency situations where a exposure in excess of 25 rem TEDE

would be required, the following additional criteria shall be considered:

a. Rescue personnel must be volunteers.

b. Rescue personnel should have a full awareness of the risks involved

(See Attachment 2).

c. Other things being equal, volunteers above the age of 45 should be

selected whenever possible for the purpose of avoiding unnecessary

genetic effects.

d. Exposure under these conditions should be limited to once in a

lifetime, and shall be included when calculating future lifetime

permissible exposures.

PEP-3 30 Rev. 5 Pace 14 of 5;2

2

JPM SRO-A.4

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM SRO-A.4

Perform an Emergency Action Level

Classification and Recommend Protective

Actions

CANDIDATE:

EXAMINER:

Page I of 14

JPM SRO-A.4

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

and Recommend

TASK: Perform an Emergency Action Level Classification

Protective Actions

ALTERNATE PATH: None

SRO-A.4 (NRC Exam - Dec 2000)

FACILITY JPM NUMBER 1

IMPORTANCE: SRO 4.1/4.0 RO NA

KA: 2.4.41 /2.4.44

F~nnwled~e of the emergency action level thresholds and

KA STATEMENT:

classifications. / Knowledge of emergency plan protective

action recommendations.

fission

TASK STANDARD: General Emergency determined due to three (3)

product barriers breached (EAL 2-1-4) AND PARs

completed satisfactorily.

SI MULATOR IN PLANT

PREFERRED EVALUATION LOCATION: SIMULATE

ERFORM

PREFERRED EVALUATION METHOD: P1

REFERENCES: Emergency Action Level Flowpath nd Protective Action

PEP-I 10, Emergency Classification an

Recommendations

CRITICAL: C

C15) MINUTES TIME

VALIDATION TIME:

CANDIDATE:

FINISH TIME:

START TIME:

PERFORMANCE TIME: MINUTES

classification during

NOTE: Performance Rating based on 20% for satisfactory JPM, and 60% for

during

simulator scenario, 20% for satisfactory classification JPM.

satisfactory protective action recommendation during

SAT UNSAT

PERFORMANCE RATING:

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 14

JPM SRO-A.4

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

PEP- 110, "Emergency Classification and Protective Action Recommendations,"

Attachment 3, "Protective Action Recommendations Process"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

I

room steps shall be performed for this JPM, including any required communications.

asked by

will provide initiating cues and reports on other actions when directed or

indicate

you. Ensure you indicate to me when you understand your assigned task. To

you.

that you have completed your assigned task, return the handout sheet I provide

INITIAL CONDITIONS:

implemented.

Following a reactor trip and safety injection, EOP-PATH-2 is being

The following plant conditions are noted:

"* All CSFSTs are currently green or yellow.

"* All ESF equipment is functioning.

"* Containment conditions are normal.

"* One SG Safety is stuck open on SG 'B'.

"* SG 'B' level is below the narrow range indication.

"* SGs 'A' and 'C' are being controlled at approximately 25% level using AFW.

"* EPP-014, Faulted Steam Generator Isolation, has been performed for SG 'B'.

"* The most recent RCS 1-131 dose equivalent sample was 89 uCi/cc.

"* The GFFD shows no increase in count rate.

"* The RCS is subcooled by 520 F.

"* Core damage assessments are NOT yet available.

"* Emergency dose projections are NOT yet available.

INITIATING CUE(S):

Point "U" as

You are to classify this event, entering the EAL Network at Entry

directed by PATH-2.

Page 3 of 14

JPM SRO-A.4

HARRIS

START TIME:

  • DENOTES CRITICAL STEP

STANDARD NOTES SAT /

JPýMPROC ELEMENT

STEP STEP UNSAT

Obtains EAL Flowpath Note that there is

NA Locates procedure and also a large

and copy of PEP-I10

required information. laminated copy of

this which may be

used.

NOTES:

1. PROCEDURE STEPS ARE NOT LISTED

SINCE ATTACHMENT 3 OF PEP- 110 IS A

FLOWCHART WHICH DOES NOT CONTAIN

NUMBERING OF STEPS.

2. NOT REQUIRED TO REFERENCE PEP-110.

3. THE FOLLOWING JPM STEPS ARE

DECISION POINTS REQUIRED TO BE MADE

TO OBTAIN THE CORRECT EAL

CLASSIFICATION AND ARE ADDRESSED

FOR THIS REASON, ALTHOUGH INOI ALL

ARE CONSIDERED CRITICAL STEPS.

Enters EAL Network at NOTE: Given in

Enters EAL Network at

Entry Point "U"and initial conditions

proper location due to being

indicates RCS Breached

on FPB Status Board directed to this

entry by PATH-2.

Directs Unit-SCO to NOTE: Crew

Initiates monitoring of

initiate monitoring should be already

Critical Safety Functions monitoring due to

being in EOP

Network.

Any Rad Mon in EAL Table <YES> Determines MS

I in High Alarm Line 'B' Rad Monitor in

high alarm

<NO> Determines rad NOTE: Given in

Plant Vent Stack #1 WRGM

monitor indicating initial conditions.

Effluent Chnl > 3.6E5

uCi/sec normal based on

Attachment A

indications

Page 4 of 14

JPM SRO-A.4

HARRIS

STANDARD NOTES SAT /

JPM PROC ELEMENT

STEP STEP UNSAT

<NO> Determines rad NOTE: Given in

6 Either Cnmt Hi Range

Accident Mon> 17.5 R/hr monitor indicating initial conditions.

normal based on

Attachment A

indications

2 Monitor > <NO> Determines rad NOTE: Given in

7 timesTable

1000 EAL

Any normal monitor indicating initial conditions.

normal based on

Attachment A

indications

<NO> Entry determined NOTE: Given in

Was Entry at Point "T" initial conditions.

to be at Point "U"

<NO> Determimes NOTE: Given in

9 GFFD increased > 1.0E5 cpm

GFFD has not increased initial conditions.

in 30 mins

<NO> Determines RCS NOTE: Given in

10 RCS Activity (1-131 Dose

Activity < 300 uCi/cc initial conditions.

Equivalent) > 300 uCi/cc

<NO> Determines Core NOTE: All

Core Cooling CSF red

Cooling Status CSF CSFSTs given as

NOT red being green or

yellow in initial

conditions.

Indicates Fuel Intact on NOTE: Later

12 Indicate Fuel Intact on FPB

FPB Status Board determination will

Status Board cause this to be

changed to

Breached.

<YES> Determines NOTE: Given in

  • 13 EOP PATH-2 entered initial conditions.

EOP PATH-2 entered

Critical to

Determine proper

EAL classification.

An incorrect

decision here

would result in

determining Fuel

intact instead of

breached.

Page 5 of 14

JPM SRO-A.4

HARRIS

STANDARD NOTES SAT /

JPM PROC ELEMENT

STEP STEP UNSAT

<YES> Determines NOTE: Given in

"*14 Any Main Steamline Rad initial conditions.

Main Steamline Rad

mon > 20 mR/hr monitor 3592 (SG 'B')

Critical to

above 20 mR/hr (21.8

mR/hr) Determine proper

EAL classification.

An incorrect

decision here

would result in

determining Fuel

intact instead of

breached.

NOTE: RCS

Indicates Fuel and RCS

Indicate Fuel and RCS already previously

15 Breached on FPB Status

Breached on FPB Status Board determined to be

Board Breached and Fuel

status now changed

from Intact to

Breached.

NOTE: Given in

<NO> Entry

"*16 Was Entry at Point "V" determined to be at

initial conditions.

Point "U"

C~ritical to

Determine proper

EAL classification.

An incorrect

decision here

would result in

determining

Containment intact

instead of

breached.

I

<YES> Determines NOTE: Safety

Is Cnmt Phase A or Vent

Phase A and Vent Injection signal

Isolation Required?

Isolation required due to required due to

Safety Injection signal SGTR (PATH-2

entered).

<NO> Determines no NOTE: No

Pathway for fission products

containment breaches indications given

to escape Cnmt exists other

exist directly to that containment is

than secondary systems

atmosphere, other than breached (intial

(steam/feed) conditions for

via SG pathway, based

on given conditions containment are

normal).

Page 6 of 14

JPM SRO-A.4

HARRIS

ELEMENT STANDARD NOTES SAT/

3PM PROC UNSAT

STEP STEP

-1

NOTE: Indicated

"*19 Primary-to-secondary <YES> Determines NOTE: Indicated

primary-to-secondary by elevated rad

leakage in any SG > 10 gpm levels, requirement

leakage in SG 'B'

exceeds 10 gpm based for reactor trip and

on being required to be safety injection.

in PATH-2

Critical to

Determine proper

EAL classification.

An incorrect

decision here

would result in

determining

Containment intact

instead of

breached.

A~ffected ýSGValves

Safety NOTE: Given in

20 < SNO> Determines one initial conditions.

shut Safety open on affected

SG

ndicates Cnmt

21 Indicate Cnmt Breached on

Breached on FPB Status

FPB Status Board

Board

<ZYES> ýDetermines all NOTE: Incorrect

  • 22 3 FPBs Breached / response to this

3 FPBs are breached

Jeopardized decision would

result in improper

classification due to

only 2 FPBs being

considered

breached.

Critical to allow

determination of

proper EAL

classification and

PARs.

General Emergency EAL 2- Determines General Critical to

1-4 exceeded Emergency EAL 2-1-4 determine proper

exceeded EAL classification

and allow

determination of

PARs.

Page 7 of 14

JPM SRO-A.4

HARRIS

STAN DARD NOTES SAT /

JPM PROC ELEMENT UNSAT

STEP

STEP

NOTE: Although

CUE: IF CANDIDATE DE DETERMINE EAL NOTE:

conditionsAlthough

are

CLASSIFICATION TO BE GENERAL different in

EMERGENCY, PROVIDE CANDIDATE WITH Attachment B,

ATTACHMENT 'A' (WIND SPEED AND same process and

DIRECTION) AND DIRECT CANDIDATE TO responses are used

NOW DETERMINE PROTECTIVE ACTION in remainder of

RECOMMENDATIONS BASED ON THIS EVENT. JPM.

CONDITIONAL CUE: IF CANDIDATE DOES

NOT DETERMINE EAL CLASSIFICATION TO BE

GENERAL EMERGENCY, PROVIDE

CANDIDATE WITH ATTACHMENT 'B' (CUE

SHEET) AND DIRECT CANDIDATE TO

DETERMINE PROTECTIVE ACTION

RECOMMENDATIONS BASED ON THIS

ATTACHED EVENT.

Locates proper procedure and Locates Protective

24 Action Recommendation

required information for

Process in PEP-I 10,

determining PAR A~-~L--tI

At\tac hmIenIt I -sn

General Emergency <YES> Determines NOTE: If using

  • 25

Declared? General Emergency Attachment B

declared based on just conditions, this

determined EAL should be YES due

to given conditions.

Critical to allow

determination of

PARs.

Page 8 of 14

JPM SRO-A.4

HARRIS

ELEMENT STANDARD NOTES SAT /

JPM PROC

UNSAT

STEP STEP

  • 26 Substantial core damage is <YES> Determines NOTE: For this

substantial core type of event,

imminent or has occurred should consider any

damage is imminent or

has occurred. Fuel Breach

sufficient to

warrant that

substantial core

damage has

occurred (See Note

4 on PAR

Flowchart).

NOTE: If using

Attachment B

conditions, this

should be YES due

to Core Damage

exceeding 1% melt.

Critical to allow

determination of

PARs.

  • 27 A significant loss of reactor <YES> Determines NOTE: For this

significant loss of type of event,

coolant is imminent or has should consider any

occurred reactor coolant is

imminent or has RCS Breach

occurred. sufficient to

warrant that

significant loss of

reactor coolant is

imminent or has

occurred (See Note

4 on PAR

Flowchart).

NOTE: If using

Attachment B

conditions, this

should be YES due

to Containment

Hydrogen

exceeding I% or a

LOCA.

Critical to allow

determination of

PARs.

Page 9 of 14

JPM SRO-A.4

HARRIS

STANDARD NOTES SAT/

JPM PROC ELEMENT

UNSAT

STEP STEP

<YES> Determines NOTE:

  • 28 Containment failure

(Primary or S/G) is containment failure Faulted/Ruptured

(S/G) is imminent or S/G with a relief

imminent or has occurred

has occurred. valve open is

considered to be an

indication that a

Containment

Breach has

occurred (See Note

3 on PAR

Flowchart).

NOTE: If using

Attachment B

conditions, this

should be YES due

to Containment

Hydrogen

exceeding 4%.

Critical to allow

proper

determination of

PARs.

Determines wind NOTE: Wind

29Determine wind direction

direction from 2200 direction is always

given "from".

Critical to

determine proper

evacuation and

sheltering

subzones.

Page 10 of 14

JPM SRO-A.4

HARRIS

STANDARD NOTES SAT/

JPM PROC ELEMENT UNSAT

STEP STEP

Determines evacuation NOTE: Based on 5

  • 30 Determine evacuation areas mile radius and

subzones to be

A,B,C,D,E,F,K,L wind direction

using 5 miles

radius /10 mile

downwind table.

Critical to

determine proper

evacuation

subzones.

NOTE: Based on

Determines shelter

"*31 Determine shelter areas subzones to be 10 miles downwind

and wind direction

G,H,I,J,M,N

radius /10 mile

downwind table.

Critical to

determine proper

sheltering

subzones.

TASK COMPLETE

STOP TIME:

Page IIof 14

JPM SRO-A.4

HARRIS

CANDIDATE ATTACHMENT B

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A GENERAL EMERGENCY has been declared following a large break loss of

coolant accident.

The following conditions are noted:

Core Exit Thermocouple temperatures are all between 1900'F and 2000'F.

Radiochemistry analysis indicates that approximately 2.6% of the fuel volume has

melted.

RHR is injecting through the RCS cold legs.

Containment Spray is operating with Containment Pressure at 18 psig.

Containment hydrogen concentration is 5.5%.

Wind Direction is 2200.

Wind Speed is 18 mph.

INITIATING CUE(S):

Determine the Protective Action Recommendations for these conditions.

Page 12 of 14

JPM SRO-A.4

HARRIS

rs

CANDIDATE ATTACHMENT A

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

WIND DIRECTION AND SPEED

"* Wind Direction is 2200.

"* Wind Speed is 18 mph.

Page 13 of 14

JPM SRO-A.4

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Following a reactor trip and safety injection, EOP-PATH-2 is being implemented.

The following plant conditions are noted:

"* All CSFSTs are currently green or yellow.

"* All ESF equipment is functioning.

"* Containment conditions are normal.

"* One SG Safety is stuck open on SG 'B'.

"* SG 'B' level is below the narrow range indication.

"* SGs 'A' and 'C' are being controlled at approximately 25% level using AFW.

"* EPP-014, Faulted Steam Generator Isolation, has been performed for SG 'B'.

"* The most recent RCS 1-131 dose equivalent sample was 89 uCi/cc.

"* The GFFD shows no increase in count rate.

"* The RCS is subcooled by 52°F.

"* Core damage assessments are NOT yet available.

"* Emergency dose projections are NOT yet available.

<-V

RADIATION MONITORING PANEL INDICATIONS

NOTE: Assume all radiation monitors NOT included in this list are indicating at or near

their normal value.

I MONITOR DESCRIPTION READING / ALARM STATUS

REM-ITV-3536 Turbine Building Stack 3A 3.2E-4 uCi/sec/Normal (Green)

REM-ITV-3534 Cond Vac Pump Effluent Lowering / Was High (Red), now

Alert (Yellow)

REM-1BD-3527 Steam Generator Blowdown Lowering / Was High (Red), now

Alert (Yellow)

RM-IMS-3591-SB Main Steam Line 'A' 0.8 mR/hr /Normal (Green)

RM-IMS-3592-SB Main Steam Line 'B' 21.8 mR/hr / High (Red)

RM-IMS-3593-SB Main Steam Line 'C' 0.7 mR/hr/Normal (Green)

INITIATING CUE(S):

You are to classify this event, entering the EAL Network at Entry Point "U" as

directed by PATH-2.

Page 14 of 14

Attachment 3

Sheet 1 of 2

PROTECTIVE ACTION RECOMMENDATION PROCESS

5 Mile Radius, 10 Miles Downwind 2 Mile Radius 5 Miles Downwind

Evacuate Shelter Wind Evacuate Shelter

Wind

Direction Subzones Subzones

Direction Subzones Subzones

(From °)

(From 0) AD,K S,C,E,F,G,H.1,J,L,M,N

327Q - 010V

348Q- 010Q A,8,C,D,H.IK,L E,F,G,J,M,N

01IQ - 0340 AB,C,D,H,I,J,K,L E,FG,M,N 0192 - 0562 A,K B,C,D,EF,G,H,I,J,L,M,N

057-

14g A,K,L B,C,D,E,F,G,H,IJ,M,N

035Q - 079Q A,B,C,D,IJ,K,LM E,FG,HN

125Q - 1910 A,B,L C,D,E,F,G,H,I,J,K,M,N

080Q - 101Q A,B,C,D,J,KL,M E,F,G,HI,N CAE,F,GHI,J,K,L,M,N

192 - 2140 A,B

102Q - 1240 A,B,CD,J,K,L,M,N E,F,G.H,I

EF,G,HIJ 215Q - 259' A.BC D E,F,G,HI,J,K,L.MN

125Q- 146* A,B.C,D,KL,MN

260' - 281Q AB,C,D E,F,G H,I,J,K,LM,N

147Q - 1910 A,B,C,D.E,K,L,M,N F.G,H,,J

282' - 304' A.C,D B,E,F,GH,I,J,KI M,N

192Q -214Q ACD,E,K,L,N FG.HI , M

GH,I,J,M.N 305Q - 326' AC,D,K B,E,F,G,H,I,J,L.M,N

2159 - 236Q A,B,C.D,E,F,K,L

237Q - 259' A,B,C,D.E,F,G,K,L H,I,JM,N

260' - 326' A,B,C,D,F,GHKL EI,J,M,N

327'- 3470 A,B,C,D,G,H.I,K.L EF,J,M,N

PEP-110 Rev. 9 Page 16 of 22

Attachment 3

Sheet 2 of 2

PROTECTIVE ACTION RECOMMENDATION PROCESS

1. Indications that substantial core damage is imminent or has occurred include:

a) Core damage > 1% Melt.

b) Core Exit Thermocouple readings Ž>23002 F.

c) Core uncovered > 30 minutes.

2. Indications that a significant loss of reactor coolant is imminent or has occurred include:

a) Containment radiation reading > 10,000 R/Hr without spray or> 4,000 R/Hr with spray.

b) Containment hydrogen gas concentration> 1%.

c) Rapid vessel depressurization.

d) A large break loss of coolant accident.

3. Indications that containment failure (primary or S/G) is imminent or has occurred include:

a) A release of radioactivity can not be maintained below the General Emergency EAL

criteria.

b) Primary containment pressure can not be maintained below design basis pressure

which is 45 psig.

c) Primary containment H2 gas concentration can not be maintained below combustible

limits which is 4% by volume.

d) Faulted/Ruptured S/G with a relief valve open.

4. Accidents which result in a direct release pathway to the environment (for example, a

faulted and ruptured S/G with water level below the tube bundles and a relief valve open

would provide such a pathway) will most likely be thyroid dose limiting. For circumstances

involving this type of accident sequence:

a) Consider any Fuel Breach sufficient to warrant the determination that substantial core

damage has occurred.

b) Consider any RCS Breach sufficient to warrant the determination that a significant loss

of reactor coolant has occurred.

Containment monitors can provide indication of both core damage and RCS breach. Monitor

values used to determine a specific amount of core damage are dependent on plant conditions,

power history and time after shutdown. Monitor readings used to quantify an amount of damage

or coolant leakage should be complimented by other indications and engineering judgment.

Ifa release is in progress:

"* Perform dose assessment as soon as possible to determine if PAGs are exceeded and if

additional Subzones require evacuation.

"* Add any Subzones requiring evacuation as determined by dose assessment to the plant

based PARs.

Ifno release is in progress:

"* Perform dose projection on possible conditions as time permits to determine if PAGs could

be exceeded.

"* Consider adding any Subzones requiring evacuation as determined by dose projection to

the plant based PARs.

PEP-110 Rev. 9 Page 17 of 22

4.0 GENERAL

The Site Emergency Coordinator - CR and Emergency Communicator - CR

Attachments (1 and 3) contain an "Initial Actions" section. The "Initial Actions"

section is designed to guide the ERO member through the priority tasks following

initial discovery of a condition or event requiring an emergency declaration.

Specifically:

"* Event declaration is required within 15 minutes of the time that plant

parameters reach an Emergency Action Level.

"* Alerting of on site personnel via Public Address announcement is required

within 15 minutes of event declaration.

"* Notification of event declaration to the State and County officials is

required within 15 minutes of event declaration.

"* Accountability must be completed within 30 minutes of; a Site Area

Emergency or higher declaration; or decision to conduct accountability.

"* Notification of event declaration to the NRC is required "as soon as

possible" and no later than 60 minutes after an event declaration.

"* Activation of the NRC ERDS data link is required within 60 minutes of an

Alert or higher event declaration.

The Plant Operations Director attachment (2) also contains an "Initial Actions"

section. This section is designed to guide the ERO member through the priority

tasks associated with preparation for, and conduct of, the activation of the HNP

Emergency Response Facilities.

The exact circumstances may dictate that portions of the Responsibility/Activity

section be performed concurrent with the Initial Actions section of Attachments 1

-3.

PEP-230 Rev- 7 Page 4 of 34

JPM RO-A.4

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM RO-A.4

Activate the Emergency Response Organization

- Dialogic System

CANDIDATE:

EXAMINER:

Page I of 8

JPM RO-A.4

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Activate the Emergency Response Organization - Dialogic System

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

KA: 2.4.43 IMPORTANCE: SRO NA RO 2.8

KA STATEMENT: Knowledge of emergency communications systems and

techniques

TASK STANDARD: The Emergency Response Organization has been notified of

a plant emergency using the Dialogic System

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PERFORM SIMULATE

PREFERRED EVALUATION METHOD:

REFERENCES: PEP-3 10, Notifications and Communications

VALIDATION TIME: 15 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

JPM RO-A.4

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

Telephone System

PEP-3 10, "Notifications and Communications," Attachment 6, "Emergency Response

Organization Activation - Dialogic System"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

room steps shall be performed for this JPM, including any required communications. I

will provide initiating cues and reports on other actions when directed or asked by

you. Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

"ASite Area Emergency has been declared. It is currently 1030 on Saturday morning.

"APublic Address System announcement directing on-site members of the ERO to

activate the Emergency Response Facilities has been made.

INITIATING CUE(S):

You have been directed to initiate activation of the remainder of the ERO using PEP

3 10, "Notifications and Communications," Attachment 6, "Emergency Response

Organization Activation - Dialogic System."

Page 3 of 8

JPM RO-A.4

HARRIS

START TIME:

  • DENOTES CRITICAL STEP

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT

T.....I

1-

I NA Obtain procedure Obtains copy ot PEP

3 10, Attachment 6

NOTE: PROCEDURE STEPS CORRESPOND TO

STEPS IN ATTACHMENT 6. CUES LISTED

SHOULD BE READ DIRECTLY AS WRITTEN AS

AUTOMATIC RESPONSES TO OPERATOR

ACTIONS.

2 Scenario Determination - Selects scenario number

Select the appropriate "23" based on a Site

scenario number from the Area Emergency

provided options occurring during off

normal hours (weekend)

  • 3 2A Connecting to the System Picks up a plant Critical to connect

extension and dials to system to

Dial 2452 on a plant "2452" establish operation.

extension or dial 362

2452 if using a Southern

Bell line

CUE: "HELLO"

  • 4 2B Immediately enter 4357 Enters "4357#" Critical to establish

immediately upon proper connection

followed by the "#" key.

hearing "hello" to system.

response

CUE: "ENTER THE SCENARIO NUMBER YOU

WISH TO WORK WITH."

  • 5 2C Enter the appropriate Enters "23#"

Critical to enter

proper scenario

scenario number followed number to ensure

by the "'" key correct notification.

Page 4 of 8

JPM RO-A.4

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT

CUE: "YOU ENTERED 23. IS THAT CORRECT?

PLEASE PRESS 9 FOR YES, 6 FOR NO."

  • 6 2D If correct, enter 9 Enters "9" Critical to validate

proper plant

conditions.

CUE: "THE SELECTED SCENARIO HAS BEEN

COMPLETED. DO YOU WANT TO QUEUE IT?

PLEASE PRESS 9 FOR YES, 6 FOR NO."

  • 7 2E Enter 9 Enters "9" Critical to direct

system to begin

making calls.

CUE: "YOU WILL QUEUE SCENARIO 23 AS AN

EMERGENCY. ARE YOU SURE THIS IS WHAT

YOU WANT TO DO? PLEASE PRESS 9 FOR YES,

6 FOR NO."

  • 8 2F Enter 9 Enters "9" Critical to direct

system to begin

making calls.

CUE: "PRESS 1 TO STOP SCENARIO MONITOR

OR PRESS 2 TO SPEAK OF THE STATUS. THE

SELECTED SCENARIO IS ACTIVE, GOODBYE."

9 2G Hang up and prepare for Hangs up phone Note: The previous

system activation verification message should be

(System will soon dial disregarded as this

telephones in the MCR (362- a system default

7992 or 362-7997)). message not

associated with

the ERO activation

process at Harris.

CUE: PHONE LINE 362-7997 RINGS.

Page 5 of 8

JPM RO-A.4

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

  • 10 3A System Activation Picks up line 362-7997 Critical to answer

Verification - phone to provide

When one of the Direct Bell verification of

lines rings, answer the system start.

telephone

CUE: "PLEASE ENTER A 2 FOLLOWED BY

YOUR SOCIAL SECURITY NUMBER."

  • 11 3B Enter 2-123-45-6789 Enters "2123456789" Critical to enter

number to verify

actual event

occurring requiring

notification.

CUE: "YOU ENTERED 2-123-45-6789 IS THAT

CORRECT? PLEASE PRESS 9 FOR YES, 6 FOR

NO."

"*12 3C If correct, enter 9 Enters "9" Critical to verify

previous

information to start

system.

CUE: "THE EMERGENCY CLASSIFICATION IS

SITE AREA EMERGENCY. ARE YOU FIT FOR

DUTY?"

"*13 30 Enter 9 Enters "9" Critical to respond

with 'yes' response

to start system.

CUE: "YOU WILL BE FILLING THE POSITION

OF MAIN CONTROL ROOM. PLEASE ENTER

YOUR ETA IN MINUTES."

"*14 3E Enter 00 Enters "00" Note that any

number entry will

work for this entry.

Critical to enter any

number to initiate

Sdialing system. _____

Page 6 of 8

JPM RO-A.4

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT

CUE: "THANK YOU. GOODBYE."

15 3F If the computer functioned as Notifies SEC-CR that

expected, notify the SEC-CR Dialogi c is calling in the

that Dialogic is calling in the ERO

ERO

16 4 Completion - Signs aind dates Previous step

actually informed

Inform SEC-CR of the results compleltion of

notificat ion SEC-CR verbally.

of the system activation

TASK COMPLETE

STOP TIME:

Page 7 of 8

JPM RO-A.4

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A Site Area Emergency has been declared. It is currently 1030 on Saturday morning.

A Public Address System announcement directing on-site members of the ERO to

activate the Emergency Response Facilities has been made.

INITIATING CUE(S):

You have been directed to initiate activation of the remainder of the ERO using PEP

310, "Notifications and Communications," Attachment 6, "Emergency Response

Organization Activation - Dialogic System."

Page 8 of 8

JPM COM-B. L.a

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM COM-B. 1.a

Respond to a Failed High Pressurizer

,j(7

Pressure

Channel

\ I

CANDIDATE:

EXAMINER:

Page I of 8

JPM COM-B. I.a

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Respond to a Failed High Pressurizer Pressure Channel

ALTERNATE PATH: Pressurizer PORV fails to reseat following actuation

FACILITY JPM NUMBER: NEW

KA: 010.A2.03 IMPORTANCE: SRO 4.2 RO 4.1

KA STATEMENT: Ability to correct, control, or mitigate the consequences of

the following PRZ PCS malfunction: PORV failures

TASK STANDARD: Master PRZ Controller is in MANUAL, controlling pressure,

with PORV Block Valve 1RC-1 13 closed.

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PERFORM SIMULATE

PREFERRED EVALUATION METHOD:

REFERENCES: AOP-019, Malfunction of RCS Pressure Control

VALIDATION TIME: 10 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

JPM COM-B. I.a

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

  • Initialize to a 100% power IC.
  • Enter malfunction to fail PRZ Pressure Channel 444 high and cause PORV to fail to

reseat <IMF PRS03F 1 0> <PT:444 2500 0>.

  • FREEZE the simulator.
  • When candidate is ready, place simulator in RUN.

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

room steps shall be performed for this JPM, including any required communications. I

will provide initiating cues and reports on other actions when directed or asked by

you. Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

The plant is operating at 100% power.

The following alarms have been received:

"* PRESSURIZER HIGH PRESS DEVIATION CONTROL (ALB-009-3-1)

"* PRESSURIZER RELIEF DISCHARGE HIGH TEMP (ALB-009-8-2)

"* PRESSURIZER HIGH-LOW PRESS (ALB-009-5-1)

"* PRESSURIZER RELIEF TANK HIGH-LOW LEVEL PRESS OR TEMP (ALB-009-8- 1)

INITIATING CUE(S):

You are to respond to the alarm condition(s), performing any required Immediate

Actions from memory.

Page 3 of 8

JPM COM-B. L.a

HARRIS

START TIME:

  • DENOTES CRITICAL STEP

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP UNSAT

STEP

I _______________

I 3.0.1 (IMMEDIATE ACTION) Determines bubble

Check that a bubble exists in exists due to plant

4- the PRZ conditions

  • 2 3.0.2 (IMMEDIATE ACTION) "* Determines PORV ,Critical to isolate the

444B failed to fullyV/ PORV to prevent

Verify all PRZ PORVs and RPS and/or ESF

close as pressure

associated block valves actuation on low

lowers

properly positioned for pressure.

current PRZ pressure and "* Attempts to close

plant conditio7ns PRZ PORV 444B by

placing control Only critical to close

switch in CLOSE PORV isolation

valve.

"* Closes PRZ PORV

444B isolation Z

valve, RC-1 13 V

  • 3 3.0.3 (IMMEDIATE ACTION) Takes manual control Critical to close the

Check both PRZ spray of pressurizer spray

valves by either: y

rray valves to

prevent RPS and/or

valves properly positioned ESF actuation on

for current PRZ pressure "* Placing master

low pressure.

and plant conditions. V 7 controller PK-ý4j?ýL

in manual, or'C

"* Placing spray Only critical to

valves in manual cause spray valves

-2W Ho close, not perform

both actions.

NA Obtain procedure Obtain current copy 0 or

AOP-0 19, Sections 3.

and 3.1

3.0.4 Go to Section 3.1, Pressure Refers to Section 3.1

5

Control Malfunctions While

Bube

Operating With a Pressurizer

I I ~Bubble. _______

Page 4 of 8

JPM COM-B.I.a

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

3.1.1 Refer to PEP- 110, Informs SRO of need to

Emergency Classification refer to PEP-I 10

and Protective Action

Recommendations, and enter

the EAL Network at entry

point X.

CUE: INFORM CANDIDATE THAT OTHER

OPERATORS WILL PERFORM EAL NETWORK

CHECKS.

7 3.1.2 (CONTINUOUS ACTION) Monitors PRZ pressure

Monitor PRZ pressure by by observing one or

observing other reliable more of the following:

indication. * PI-455.1

  • PI-456
  • PI-457

8 3.1.3 Check plant in Mode I or 2. Determines plant in

Mode I by conditions

9 3.1.4 (CONTINUOUS ACTION) Determines PRV

Check PRZ pressure pressure is controlled

controlled. using PK-444A in

MANUAL

Determines pressure is -I t

I I _____________________________________ .L.

10 I 3.1.5 (CONTINUOUS ACTION) <_2335 psig

Check PRZ pressure 2335

psig or less.

  • 11 3.1.6 Check all of the following "* Determines PRZ Critical to ensure I

PORV block valves hour TS requirement

PRZ PORV block viives

open: for closed block

open or Refer to Technical

"* IRC-117 valve is met.

Specification 3.4.4 and

implement action where "* IRC-115

appropriate: "* Determines PRZ

445A SA) . IRC- 113 closed.

  • IRC-115 (for PCV "* Informs SRO of

445B) .- need to refer to TS

444B SB) L____- -7

CUE: INFORM CANDIDATE THAT OTHER

OPERATORS WILL REFER TO TECH SPECS.

Page 5 of 8

JPM COM-B.

HARRISI.a

NOTES SAT/

UNSAT

JPM

STEP PROC

STEP ELEMENT STANDARD

Determines that PT-444

12 3.1.7 Check that a malfunction of has failed high by

one or more of the following comparing it to other

has occnrred:7 channels.

( PK-444A

  • PRZ heater(s)
  • PRZ spray valve(s) or

controller(s)

Verifies PK-444A was

3.1.8 Verify PK-444A in

13 placed in MANUAL as

MANUALV,"

part of Immediate

Actions.

Adjusts PK-444A Critical of

to PRZ

maintain

"71*t4 3.1.9.a Control PRZ pressure as output by depressing

control

follows: the UP or DOWN pressure.

  • Adjust PK-444A buttons as required to

output as necessary, to control pressure

attempt to restore and

maintain PRZ

pressure.

  • Checks both spray Only critical to

"*15 3.1.9.b (CONTINUOUS ACTION) control spray valve

valve controllers

0 - Check both PRZ spray

valve controllers in. operating properly if positions to control

in auto PRZ pressure if

AUTO and both, spray

- Manually operates spray valves are in

Iva-'es operating

kr spray controllers as manual control.

desired, OR

  • Verify both PRZ spray needed by

depressing UP or NOTE: If spray

valve controllers in

DOWN buttons if valve controllers

MANUAL and operate

in manual were previously

spray valves as

placed in manual

necessary to control they are to remain in

P112 pressure manual.

16 .9.c (CONTINUOUS ACTION) Checks heaters operating

"* Check all PRZ heaters properly for pressure

operating as desired, R

"* Manually operate

control switches for

heater groups as

necessary to control

LPRZ pressure.

Page 6 of 8

JPM COM-B. I.a

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT]

17 31 Check at least one of the * Determines

following conditions present, pressure, spray

or go to Step 18: valves, and heaters

"* PRZ pressure is are controlled

uncontrolled * Goes to Step 18

"* Status of a normal spray

valve or a PRZ heater

bank is uncontrolled

INFORM CANDIDATE THAT TASK IS

COMPLETE WHEN DETERMINATION MADE

THAT RCS PRESSURE, HEATERS, AND SPRAYS

ARE UNDER CONTROL.

STOP TIME:

Page 7 of 8

JPM COM-B. I.a

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is operating at 100% power.

The following alarms have been received:

PRESSURIZER HIGH PRESS DEVIATION CONTROL (ALB-009-3-1)

PRESSURIZER RELIEF DISCHARGE HIGH TEMP (ALB-009-8-2)

PRESSURIZER HIGH-LOW PRESS (ALB-009-5-1)

PRESSURIZER RELIEF TANK HIGH-LOW LEVEL PRESS OR TEMP (ALB-009-8-1 )

INITIATING CUE(S):

You are to respond to the alarm condition(s), performing any required Immediate

Actions from memory.

Page 8 of 8

JPM COM-B.I.b

HARRIS

ar-ý6

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM COM-B. 1.b

LOSP While Paralleling EDG from MCB for

Testing

CANDIDATE:

EXAMINER:

K->

Page Iof 8

JPM COM-B. L.b

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: LOSP While Paralleling EDG from MCB for Testing

ALTERNATE PATH: EDG output breaker 126 fails to open on LOSP and must be

manually opened

FACILITY JPM NUMBER: NEW

KA: 056AA2.14 IMPORTANCE: SRO 4.6 RO 4.4

KA STATEMENT: Determine as related to a Loss of Offsite Power: Operational

status of EDGs

TASK STANDARD: EDG B output breaker 126 has been manually opened

PREFERRED EVALUATION LOCATION: SIMULATOR *1'

IN PLANT

PERFORM SIMULATE

PREFERRED EVALUATION METHOD:

REFERENCES: OP-155, Diesel Generator Emergency Power System

VALIDATION TIME: 15 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

JPM COM-B. I.b

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

  • Initialize the simulator to a 100% power condition.

SEE INSTRUCTIONS AFTER STEPS 17 AND 22 TO ENTER ADDITIONAL

MALFUNCTIONS.

"* STEP 17 - Prevent EDG B breaker 126 from automatically opening on subsequent

LOSP (allowing manual operation to open).

"* STEP 22 - <EPSOI> To cause a loss of offsite power to the plant.

  • Place simulator in FREEZE.
  • When candidate is ready, place simulator in RUN.

OP- 155, "Diesel Generator Emergency Power System"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

room steps shall be performed for this JPM, including any required communications. I

will provide initiating cues and reports on other actions when directed or asked by

you. Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

The plant is operating at 100% power.

Emergency Diesel Generator IB-SB has been started and is ready to be paralleled to

the grid.

INITIATING CUE(S):

You have been directed to parallel EDG IB-SB to the grid in accordance with OP- 155,

"Diesel Generator Emergency Power System," Section 5.3.

Page 3 of 8

JPM COM-B. L.b

HARRIS

START TIME:

  • DENOTES CRITICAL STEP

Page 4 of 8

JPM COM-B. l.b

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEPUSA

S~rrM-pTUNSAT

8 5.3.2.4.a Position DIESEL GEN B-SB Adjust EDG B Auto

AUTO VOLTAGE ADJUST Voltage Adjust until

control switch to RAISE or EDG voltage indicates

LOWER as necessary to 6.6 KV

perform the following:

  • Lower voltage to 6.6 KV

9 5.3.2.4.b Raise voltage to 7.2 KV Adjust EDG B Auto

Voltage Adjust until

EDG voltage indicates

7.2 KV

10 5.3.2.4.c Position DIESEL GEN B-SB Adjust EDG B Auto

AUTO VOLTAGE ADJUST Voltage Adjust until

control switch to RAISE or EDG voltage matches

LOWER as necessary to 6.9KV Bus I B-SB

perform the following: voltage (0 A VOLTS)

  • Adjust EDG voltage to

match the associated

Emergency 6.9KV Bus

voltage as indicated by

zero differential voltage

on EI-6953B SB, B

SYNC A VOLTS

11 5.3.2.5.a Position DIESEL GEN B-SB Adjust EDG B Governor

GOVERNOR CONTROL Control until EDG B

switch to RAISE or LOWER frequency is indicating

as necessary to perform the 59 HZ

following:

  • Lower frequency to 59

HZ

12 5.3.2.5.b * Raise frequency to 61 HZ Adjust EDG B Governor

Control until EDG B

frequency is indicating

61 HZ

13 5.3.2.5.c Position DIESEL GEN B-SB Adjust EDG B Governor

GOVERNOR CONTROL Control until EDG B

switch to RAISE or LOWER sync scope is indicating

as necessary to perform the slow CW movement

following:

  • Adjust EDG speed until

the synchroscope is

rotating slowly in the

FAST direction

(CLOCKWISE)

Page S of 8

JPM COM-B. I.b

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

I _ _ _ _ _ _ _ _ _ _I t

14 5.3.2.6 Check synchronizing lights Verify sync lights

are cycling (OUT when the cycling properly in

synchroscope is at the 12 agreement with sync

o'clock position) in agreement scope

with the synchroscope

rotation

15 15.3.2.7 As necessary, position Readjust EDG B Auto

DIESEL GEN B-SB AUTO Voltage Adjust until

VOLTAGE ADJUST EDG voltage matches

control switch to adjust EDG 6.9KV Bus IB-SB

voltage to zero differential voltage (0 A VOLTS)

voltage on EI-6953B SB , B

SYNC A VOLTS

"*16 5.3.2.8 When the synchroscope Place EDG B breaker Critical to close

126 to close position EDG breaker 126

reaches the 12 o'clock

when sync scope to permit EDG to

position and the

indicates 12 o'clock pickup load

synchronizing lights are

TOTALLY DARK, place position and sync lights

the DIESEL GEN B-SB are totally dark

BREAKER 126 SB control

nviteh to ClOSE.

17 5.3.2.9 Check DIESEL GEN B-SB Verify EDG B breaker is

BREAKER 126 SB is closed closed

SIMULATOR INSTRUCTOR INSTRUCTIONS:

INSERT MALFUNCTION TO PREVENT EDG B

BREAKER 126 FROM AUTOMATICALLY

OPENING ON SUBSEQUENT LOSP (ALLOWING

MANUAL OPERATION TO OPEN).

"18 5.3.2.10 Position DIESEL GEN B- Adjust EDG B Critical to pickup

SB GOVERNOR Governor Control until load to prevent

CONTROL switch to EDG B load indicates reverse power

increase generator load to 2.2 to 2.4 MW trip of EDG

2.2 to 2.4 MW on El- breaker 126

6957B1 SB, B POWER

19 5.3.2.11 Position DIESEL GEN IB- Adjust EDG B Auto

SB AUTO VOLTAGE Voltage Adjust until

ADJUST control switch to EDG reactive load

obtain 1.0 MVARs on EL- indicates 1.0 MVARs

6958B SB, B REACTIVE

20 5.3.2.12 Place DIESEL GEN B-SB Place EDG B sync scope

SYNCHRONIZER control off

switch to OFF

i'age 6 of'8

JPM COM-B. L.b

HARRIS

NOTES SAT /

JPM PROC ELEMENT STANDARD

UNSAT

STEP STEP

21 5.3.2.13 Check DIESEL GEN B-SB Verify amber light lit on

BREAKER 126 SB amber EDG B breaker 126

light is lit

22 5.3.2.l4.a Increase load per the Maintain 2.2 to 2.4 MW

following loading schedule to load on EDG B

attain desired loading AND as

load is increased, adjust

voltage to maintain reactive

load within the limits of

Attachment 9:

  • Maintain 2.2 to 2.4 MW

and MVAR within

Attachment 9 until Diesel

Exhaust temperatures

stabilize

SIMULATOR INSTRUCTOR INSTRUCTIONS:

INSERT MALFUNCTION <EPS01> TO CAUSE A

LOSS OF OFFSITE POWER TO THE PLANT.

23 NA Determine LOSP has * Determine EDG B

2*, occurred and check for proper breaker 126 has

response of EDG B output failed to open

breaker 126 * Notifies Unit SCO

Critical to

  • 24 4.0.0.024 Open EDG B breaker 126 Place EDG B breaker separate EDG

126 to open

from grid to

prevent EDG

damage due to

overload

TASK COMPLETE

STOP TIME:

Pag. / of 8

JPM COM-B. L.b

HARRMS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is operating at 100% power.

Emergency Diesel Generator IB-SB has been started and is ready to be paralleled to

the grid.

INITIATING CUE(S):

You have been directed to parallel EDG 1B-SB to the grid in accordance with OP-155,

"Diesel Generator Emergency Power System," Section 5.3.

Page8 of8

JPM COM-B. 1.c

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM COM-B. 1.c

Secure One Train of CCW to the RHR HXs

CANDIDATE:

EXAMINER:

Page I of 6

JPM COM-B.I.c

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Secure One Train of CCW to the RHR HXs

ALTERNATE PATH: None

FACILITY JPM NUMBER: RO-B. i.e (NRC Exam - Dec 2000)

KA: 008A2.01 IMPORTANCE: SRO 3.3 RO 3.1

KA STATEMENT: Ability to operate and / or monitor in the control room:

CCW indications and controls.

TASK STANDARD: Train 'A' CCW is supplying the RHR HX and the non

essential loop.

SIMULATOR IN PLANT

PREFERRED EVALUATION LOCATION:

PERFORM SIMULATE

PREFERRED EVALUATION METHOD:

REFERENCES: OP- 145, Component Cooling Water

VALIDATION TIME: 10 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 6

JPM COM-B. L.c

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

  • Initialize to an IC where RHR Train 'A' is in operation (IC-2).
  • Ensure both 'A' and 'B' CCW pumps are operating.
  • Ensure the following valves are open: ICC- 147, ICC-I167, 1CC- 113, and ICC-I127.
  • Ensure the following valves are closed: ICC-99 and ICC-128.
  • Adjust CCW flows <MRF CCW030 25>
  • FREEZE the simulator
  • When candidate is ready, place simulator in RUN

OP- 145, "Component Cooling Water," Section 8.14

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

I

room steps shall be performed for this JPM, including any required communications.

will provide initiating cues and reports on other actions when directed or asked by

you. Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

The plant is in Mode 4. Train 'B' RHR has been removed from service.

Both trains of CCW are in operation, with Train 'A' CCW supplying only the essential

loop and Train 'B' CCW supplying the essential and non-essential loops.

INITIATING CUE(S):

You are to secure CCW Pump 'B' in accordance with OP-145, Section 8.14.

Page 3 of 6

JPM COM-B. 1.c

HARRIS

START TIME:

  • DENOTES CRITICAL STEP

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP j /&-A C UNSAT

77ILI=

Obtain current copy of

1 NA Obtain procedure OP-145, Section 8.14

Critical to

"* Closes 1CC-167,

  • 2 8.14.2.1.1 IftheRHRtrain to be establish flow

CCW FROM RHR

taken out of service is limitations within

HEAT

being supplied by the same the capability of a

EXCHANGER B

CCW pump as the Non SB single pump

Essential loop then

perform the following "* Verifies the valve Verification is not

steps: closed by position critical

indicating lights

"* For the RHRHX to be

taken out of service,

Shut ICC-167, CCW

FROM RHR HEAT

EXCHANGER B-SB

Verifies total system

3 .14.2.1.2 "* Verify total system flow flow is less than 12,000

is less than 12,650 gpm

gpm by adding the

indication on FI-652.1

and FI-653.1

Verify open, the following * Places 1CC-99 Critical to allow

  • 4 8.14.2.1.3

control switch in supplying the non

valves:

  • lCC-99, CCW HEAT OPEN essential loop

EXCHANGER A TO a Places ICC-128 from the running

control switch in ccw pump

NONESSENTIAL SUP

  • 1CC- I13, CCW HEAT OPEN

EXCHANGER B TO * Verifies all valves Only critical to

now open by open ICC-99 and

NONESSENTIAL SUP

observing position ICC-128

NONESSENTIAL indicating lights

RETURN TO HEADER

B

NONESSENTIAL

RETURN TO

HEADER A

Page 4 of 6

JPM COM-B. 1.c

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

I I _____________________ I

  • 5 8.14.2.1.4 At the MCB, stop the "* Places CCW Pump Critical to

IB-SB control establish a single

desired CCW Pump A-SA

switch in STOP running CCW

or B-SB

"* Verifies the pump pump

stops by observing

breaker indicating Verification is not

lights critical

6 I 8.14.2.1.5 Verify Train B flow stops Verifies flow stops by

via FI-653.1 and that observing FI-653.1

pressure remains greater decreases to zero and

than 62 psig as per PI-650 pressure remains >62

psig on PI-650

7 8.14.2.2 If the RHR train to be taken Determines RHR train is

out of service is the only not the only flowpath for

flowpath for the CCW the CCW pump and does

pump, perform the following not perform Step

steps: 8.14.2.2

TASK COMPLETE -L _________________________________________________________________

STOP TIME:

Page 5 of 6

JPM COM-B.

HARRIS,c

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is in Mode 4. Train 'B' RHR has been removed from service.

essential

Both trains of CCW are in operation, with Train 'A' CCW supplying only the

loop and Train 'B' CCW supplying the essential and non-essential loops.

INITIATING CUE(S):

You are to secure CCW Pump 'B' in accordance with OP-145, Section 8.14.

& JPM COM-B. I .d

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM COM-B. 1.d

Manually Align Containment Spray

CANDIDATE:

EXAMINER:

Page I of 6

JPM COM-B. I .d

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Manually Align Containment Spray

ALTERNATE PATH: Starts Containment Spray and aligns valves

FACILITY JPM NUMBER: CR- 106

KA: 026A4.01 IMPORTANCE: SRO 4.3 RO 4.5

KA STATEMENT: Manually operate in the control room: CSS controls.

TASK STANDARD: Containment Spray has been actuated and all RCPs have

been stopped.

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PREFERRED EVALUATION METHOD: PERFORM SIMULATE

REFERENCES: EOP-PATH-1

VALIDATION TIME: 10 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 6

JPM COM-B.I.d

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

  • Initialize to a 100 percent condition.
  • Defeat Hi-3 Containment Pressure Signal such that Containment Spray and Phase B Isolation

are not actuated. <ZRPK:519A, ZRPK:519B>

"* Defeat the manual Containment Spray actuation switches on the MCB. <[COR ZRPK:505A,

ZRPK:505B, ZRPK:506A, ZRPK:506B>

"* Insert an RCS break of sufficient size to sustain containment pressure greater than 10# and

follow PATH-I to Step 10-- CNMT PRESSURE REMAINED BELOW 10 PSIG. <IMF

RCS I8A 80>

  • Maintain RCPs operating.
  • Place simulator in FREEZE
  • When candidate is ready, place simulator in RUN

EOP-PATH-I and EOP-PATH-I Guide

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

room steps shall be performed for this JPM, including any required communications. I

will provide initiating cues and reports on other actions when directed or asked by

you. Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

An RCS break has occurred inside containment and a reactor trip and SI have been

initiated.

PATH-I is being implemented.

INITIATING CUE(S):

Step 10ýtNMT PRESSURE REMAINED BELOW 10 PSIG,'of PATH-I has just

been reached.

Perform Step 10 of PATH-1.

Page 3 of 6

JPM COM-B. l.d

HARRIS

START TIME:

  • DENOTES CRITICAL STEP

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP ISTEP

SUNSAT

10 CNMT pressure has remained Checks pressure on

less than 10 psig MCB indicaters, ERFIS,

or Recorder Panel and

determines pressure has

exceeded 10 psig

2 10.a Verify Containment Spray Determines Containment

(RNO) actuated Spray Pumps A-SA and

B-SB NOT running

il- and/or checks ALB

001/4-I Containment

Spray ActuationrKO tBt

  • 3 10.a Manually actuate j Places Pumps in Critical to start

(RNO) Containment Spray START: pumps and position

"* Containment Spray valves to provide

Pump A-SA spray flow

"* Containment Spray

Pump B-SB

Places valves in OPEN:

"* 1CT-50, Cnmt

Spray Pump A-SA

Discharge

"* 1CT-88, Cnmt

Spray Pump B-SB

Discharge

"* ICT-12, Cnmt

Spray Chemical

Addition

"* 1CT-11, Cnmt

Spray Chemical

Addition

NOTE: MAY ATTEMPT TO MANUALLY , kc

ACTUATE SPRAY USINGIHAD CHES.

THIS WILL NOT BE SUCCESSFUL AND IS"NOT

REQUIRED TO BE PERFORMED. <-<*

Page 4 of 6

JPM COM-B. I.d

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

4 10 .a Verify Phase B Isolation Places valves in NOTE: This is

(RNO) Valves shut CLOSE: NOT considered a

"* ICC-207, CCW to critical step, and

RCPs may NOT be

"* ICC-208, CCW to performed since the

RCPs procedure does NOT

"* ICC-249, RCP direct performance.

Thermal Barriers This step will be

Return performed in Step

"* ICC-251, RCP 12 of PATH-I when

Thermal Barriers Attachment 6 is

Return performed.

"* ICC-297, RCP

Bearing Oil Coolers Candidates may

Return perform this step at

"* ICC-299, RCP this time, but it is

Bearing Oil Coolers NOT required to be

Return performed.

  • 5 10.b Stop all RCPs Places all RCPs to Critical to stop all

(RNO) STOP RCPs due to

isolating CCW

cooling flow to

RCPs

TASK COMPLETE::_

STOP TIME:

Page 5 of 6

JPM COM-B. Ie

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM COM-B. 1.e

Transfer to Hot Leg Recirculation

CANDIDATE:

EXAMINER:

Page I of 7

JPM COM-B. I.e

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Transfer to Hot Leg Recirculation

ALTERNATE PATH: Train B high head flow is re-established through cold leg

injection due to failure of hot leg injection valve to open

FACILITY JPM NUMBER: CR-066

KA: 006A4.05 IMPORTANCE: SRO 3.8 RO 3.9

KA STATEMENT: Operate in the control room: Transfer of ECCS flowpaths

prior to recirculation.

TASK STANDARD: Hot leg recirculation has been established.

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PREFERRED EVALUATION METHOD: PERFORM SIMULATE

REFERENCES: EOP-EPP-0 11, Transfer Between Cold Leg and Hot Leg

Recirculation

VALIDATION TIME: 15 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 7

JPM COM-B. I.e

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

Establish the following conditions:

  • Post-LOCA, the plant is aligned for cold leg recirculation per EPP-0 10, with SI-341

open and SI-340 closed.

  • A and B CSIPs are operating.
  • A and B RHR pumps are operating.
  • RCS pressure is approximately 0 PSIG.
  • Insert a failure for 1SI-86 to normal so it will not open <IOR XA IJ063 NORMAL>
  • Place simulator in FREEZE.
  • When candidate is ready, place simulator in RUN.

EOP-EPP-01 1, "Transfer Between Cold Leg and Hot Leg Recirculation"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

room steps shall be performed for this JPM, including any required communications. I

will provide initiating cues and reports on other actions when directed or asked by

you. Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

The plant has experienced a LB LOCA.

It has been 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> since the LOCA occurred and the plant is aligned for cold leg

recirculation per EOP-EPP-010, "Transfer to Cold Leg Recirculation."

INITIATING CUE(S):

You have been directed to perform a transfer to hot leg recirculation per EOP-EPP

011, "Transfer Between Cold Leg and Hot Leg Recirculation."

Page 3 of 7

JPM COM-B. 1.e

HARRIS

>-> START TIME:

  • DENOTES CRITICAL STEP

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

Check charging line isolated Determines charging

line is isolated by

checking charging flow

FI-122.1 indicating 0 or

by checking valves ICS

235 and ICS-238 closed

2 2 Check SI aligned for Cold Determines aligned for

Leg Recirculation Cold Leg Recirculation

by checking valves or by

checking flow on FI

943 and FI-940

  • 3 3.a Align RHR Pumps For Hot Places control power to Critical to isolate CL

Leg Recirculation: ON and then places recirc to allow

  • Shut low head SI to cold valve to CLOSED: alignment for HL

leg valves 1SI-340 and * 1SI-341, Low Head recirc

ISI-341 SI Train B to Cold

Leg Cont Pwr & Only critical to shut

VIv Pos AND Low valve SI-341 since

Head SI Train B to SI-340 is already

Cold Leg closed.

Verifies closed:

IISI-340, Low Head

SI Train A to Cold

Leg

  • 4 3.b 0 Open low head SI to hot Places control power to Critical to provide

leg valve 1SI-359 ON and then places flowpath for HL

valve to OPEN: recirc

  • lSI-359, Low Head

SI Trains A & B to

Cold Leg Cont Pwr

& Vlv Pos AND

Low Head SI

Trains A & B to

Cold Leg

Page 4 of 7

JPM COM-B. I.e

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

5 4 Check CSIP injection flow Determines valves

path: OPEN by checking

"* Alternate high head SI to position:

cold leg valve - OPEN: * 1SI-52, Alt High

ISI-52 Head SI to Cold Leg

" Any BIT outlet valve - * ISI-3, Boron Inj

OPEN: ISI-3 or ISI-4 Tank Outlet

Tank Outlet

  • 6 5.a Align both CSIPs for hot leg Places CSIP A in Critical to prevent

recirculation STOP damage to pump due

  • Stop Train A CSIP to no flowpath
  • 7 5.b * Shut alternate high Places control power to Critical to isolate CL

head SI to cold leg ON and then places recirc to allow

valve: ISI-52 valve to CLOSE: alignment for HL

Head SI to Cold

Leg Cont Pwr &

Viv Pos AND Alt

High Head SI to

Cold Leg

  • 8 5.c * Open alternate high Places control power to Critical to provide

head SI to hot leg valve: ON and then places flowpath for HL

1SI-107 valve to OPEN: recirc

Head SI to Hot Leg

Cont Pwr & Viv

Pos AND Alt High

Head SI to Hot Leg

  • 9 5.d * Start Train A CSIP Places CSIP A in Verification of

START and verifies current and flow is

current on EI-221 and NOT critical

flow on FI-940

Critical to provide

flow

  • 10 5.e * Stop Train B CSIP Places CSIP B in STOP Critical to prevent

damage to pump due

to no flowpath

II 5.f * Shut BIT outlet valves: Places valves to

ISI-3 and ISI-4 CLOSE:

Tank Outlet

Tank Outlet

Page 5 of 7

JPM COM-B. I.e

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT

12 5.g Open high head SI to hot Places control power to FAILS TO ASI-86

leg valve: I SI-86 ON and then places OPEN

valve to OPEN:

1SI-86, High Head

SI to Hot Leg Cont

Pwr & Vlv Pos

AND High Head SI

to Hot Leg

"*13 5.g.1 0 Open BIT outlet valves: Places valves to OPEN: Critical to provide

(RNO) 1SI-3 and 1SI-4 0 ISI-3, Boron Inj flowpath for CL

Tank Outlet recire since HL

Tank Outlet established

14 5.g.2 * Consult the Plant Consults Plant

(RNO) Operations Staff to Operations Staff

evaluate use of

Attachment 1 to open

High Head SI to Hot Leg

Valve while continuing

with this procedure

CUE: THE UNIT SCO WILL CONTACT THE TSC,

AND DIRECTS YOU TO CONTINUE WITH THE

PROCEDURE UNTIL A RECOMMENDATION IS

RECEIVED.

"*15 5.h * Start Train B CSIP Places CSIP B in Verification of

START and verifies current and flow is

current on EI-222 and NOT critical

flow on FI-943

Critical to provide

flow

TASK COMPLETE

STOP TIME:

Page 6 of 7

JPM COM-B. L.e

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant has experienced a LB LOCA.

It has been 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> since the LOCA occurred and the plant is aligned for cold leg

recirculation per EOP-EPP-010, "Transfer to Cold Leg Recirculation."

INITIATING CUE(S):

You have been directed to perform a transfer to hot leg recirculation per EOP-EPP

011, "Transfer Between Cold Leg and Hot Leg Recirculation."

Page 7 of 7

JPM COM-B. Lf

HARRIS

REGION II1

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM COM-B. 1.f

Start an RCP Following Maintenance

CANDIDATE:

EXAMINER:

Page I of 6

JPM COM-B. l.f

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Start an RCP Following Maintenance

ALTERNATE PATH: None

FACILITY JPM NUMBER: CR-005

KA: 003A4.06 IMPORTANCE: SRO 2.9 RO 2.9

KA STATEMENT: Operate in the Control Room: Reactor Coolant Pump

parameters

TASK STANDARD: RCP A has been started

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PREFERRED EVALUATION METHOD: PERFORM SIMULATE

REFERENCES: OP- 100, Reactor Coolant System

VALIDATION TIME: 10 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of6

JPM COM-B. L.f

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

  • Initialize the simulator to a Mode 3 hot standby condition, 557 0 F and 2235 psig <IC

7>

  • Allow simulator to run until plant conditions are stable, then FREEZE
  • When candidate is ready, place simulator in RUN

OP-100, "Reactor Coolant System," Section 5.1

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

room steps shall be performed for this JPM, including any required communications. I

will provide initiating cues and reports on other actions when directed or asked by

you. Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

The plant is in Mode 3, 557°F and 2235 psig.

RCP A was out of service for maintdnance. Maintenance has been completed and the

RCP is ready for operation

INITIATING CUE(S):

You have been directed to start RCP A in accordance with OP- 100, "Reactor Coolant

System," Section 5.1. All initial conditions have been completed.

Page 3 of 6

JPM COM-B. I ,f

HARRIS

START TIME: iO/ r

  • DENOTES CRITICAL STEP

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

I NA Obtain procedure Obtains copy of OP- 100

2 5.1.2.1.a Verify the following before Verifies RCS pressure >

pump start: 325 psig (May not

1lfjogging RCPs per GP- check - not applicable to

001, RCS pressure > 325 start) ,'.

psig

3 5.1.2.1.b * No. I seal Ap >200 psid Verifies RCP A seal Ap

> 200 psid. (PI-156A1) _ --

4 5.1.2.1.c * Seal injection flow is Verifies RCP A seal

between 8 and 13 gpm at injection flow indication

a temperature between (FI-130A) and VCT

60'F and 130'F outlet temp indication /

(TI- 116.1) in limits

5 5.1.2.1.d * No. I seal leakoff is in Verifies RCP A seal

the normal operating leakoff meets . ,

range of Attachment 3. Attachment 3 require

ments (FR- 154A)

  • 6 5.1.2.2 Start the RCP oil lift pump Places RCP A oil lift Critical to meet

pump switch to start interlock for

starting

7 5.1.2.3 Verify the amber permissive Verifies amber permis

light on the lift pump control sive light on the RCP A

switch is lit indicating proper oil lift pump switch is lit ,

lift oil pressure has been

achieved

8 5.1.2.4 Allow the RCP oil lift pump Verifies a minimum of 2

to run for a minimum of 2 minutes has passed since

minutes before starting an starting the pump

RCP

  • 9 5.1.2.5 Start the RCP Places RCP A switch to Critical to close

start breaker for RCP V

Page 4 of 6

JPM COM-B. I.f

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

10 5.1.2.6 Verify the following normal Verifies parameters are

operating parameters: in the normal band

"* Running amps: Hot 460 0 Running amps

0 RCS flow ,.

to 540 amps, Cold 715

amps * No. I sealAp

"* RCS flow::> 98% 0 No. I seal leakoff"

"* No. I seal Ap: > 200 psid * Motor winding..r

"* No. I seal leakoff: in the temperature

normal operating range of

Attachment 3

"* Motor winding

temperature: < 300TF

11 5.1.2.7 After at least 1 minute, stop Verifies one minute has

the RCP oil lift pump passed and places RCP

A oil lift pump switch to

off

TASK COMPLETE

STOP TIME:

Page 5 of 6

JPM COM-B. I.f

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is in Mode 3, 557°F and 2235 psig.

RCP A was out of service for maintenance. Maintenance has been completed and the

RCP is ready for operation

INITIATING CUE(S):

You have been directed to start RCP A in accordance with OP- 100, "Reactor Coolant

System," Section 5.1. All initial conditions have been completed.

Page 6 of 6

JPM SRO-B. lg

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM SRO-B.1.g

Power Range NI Gain Adjustment

CANDIDATE:

EXAMINER:

Page I of 7

JPM SRO-B. I.g

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Power Range NI Gain Adjustment

ALTERNATE PATH: None

FACILITY JPM NUMBER: NEW

KA: 015A4.02 IMPORTANCE: SRO 3.9 RO NA

KA STATEMENT: Operate in the Control Room: NIS Indicators

TASK STANDARD: Gain has been adjusted within limits for PR Channel N-44

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PREFERRED EVALUATION METHOD: PERFORM SIMULATE

REFERENCES: OP-ýýore Nuclear Instrumentation

VALIDATION TIM.E: ( MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 7

JPM SRO-B. l.g

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

  • Initialize to a 100% equilibrium condition
  • Place Rod Control in MAN
  • Place Meter Rate on front of PR channel NI-44 to Fast
  • Unlock gain pot on the front of PR channel NI-44
  • Slowly adjust the gain to 1.56 and verify that it indicates approximately 3% - 3.5%

below the other 3 PR channels

  • Ensure any alarms caused by this adjustment are reset
  • Lock gain pot
  • Place Meter Rate on front of PR channel NI-44 to Slow
  • Place Rod Control in AUTO
  • FREEZE the simulator
  • When candidate is ready, place simulator in RUN

OP-105, "Excore Nuclear Instrumentation," Section 8.3 and Attachment 2

(Provide marked up copy of Attachment 2 to candidate)

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All control

room steps shall be performed for this JPM, including any required communications. I

will provide initiating cues and reports on other actions when directed or asked by

you. Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

The plant is at 100% equilibrium conditions.

Following maintenance on PR Channel N-44, all required testing has been completed

and the channel is ready to be returned to service. A calorimetric has just been

performed per OST- 1004, "Power Range Heat Balance, Computer Calculation, Daily

Interval, Mode 1 (Above 15% Power)."

The calculated power is 99.8%. Indicated power on PR channel N-44 at the time of

the calorimetric was at its current value. Rod Control is in Automatic.

INITIATING CUE(S):

You are to perform the Power Range NI Gain Adjust for PR channel N-44 in

accordance with OP-105, "Excore Nuclear Instrumentation," Section 8.3 and

Attachment 2.

SPage 3 of 7

JPM SRO-B. l.g

HARRIS

START TIME: I1L15'

I-s

  • DENOTES CRITICAL STEP

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

NA Obtains procedure Obtains current copy of

OP- 105, Attachment 2

NOTE:

"* PROVIDE CANDIDATE WITH ATTACHED

MARKED UP COPY OF ATTACHMENT 2 OF

OP-105.

qt6

"* ALL IDENTIFIED PROCEDURE STEPS ARE

FROM ATTACHMENT 2. ACTIONS ARE

ONLY TO BE PERFORMED ON PR CH N-44.

2 1 Record the as found setting of Records setting as 1.56

the GAIN potentiometer on (1.54 to 1.58)

the front of Power Range t Y,

Drawer B

3 2 Determine the difference, Calculates difference to Dete *ned b

including sign, between the be .j . subtracting indicated

calculated power and the (*ll to _0 value from 99.8%

indicated reactor power at the l.w calculated power.

time data was obtained as

follows:

CALC PWR - N44 IND qt 9-5

PWR = N44 DIFFERENCE

4 3 Determine the desired Calculates desired N-44 Determined by

indication, including sign, of indication to be 99.8% algebraically

NIS as follows: summing N-44

difference from Step

N44 PRESENT IND +/- N44 2 (JPM Step 3) and

DIFFERENCE = N44 p0y N-44 present

DESIRED IND indicated value

5 4 Calculation in Steps 2 and 3 Requests independent

independently verified, verification of

calculation

(!TE FOR PURPOSES OF THIS JPM ONLY,

jC 65" INDEPENDENT VERIFICATION WILL NOT BE

____

PERFORMED. __

Page 4 of 7

JPM SRO-B.l.g

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

6 5 Before each channel Verifies no PR trip

adjustment, verify that there bistables energized on

are no PR trip bistables TSLB-3 or TSLB-4,

energized on TSLB-3 or with exception of PR

TSLB-4, except for trip High Flux Lo Setpoint,

bistables that are manually which is manually

blocked blocked

7 6 On Drawer A, place the Places Meter Rate

METER RATE switch in switch to Fast position

FAST

  • 8 7 Before adjustment of GAIN Places Rod Bank Critical to prevent

potentiometer for N-44, the Selector switch in inadvertent rod

ROD BANK SELECTOR Manual position motion due to power

switch should be placed in mismatch circuit

MANUAL to prevent

undesired rod movement

during the adjustment

CUE: IF CANDIDATE DIRECTS RO TO PLACE

RODS IN MANUAL, DIRECT CANDIDATE TO

PERFORM ACTION TO PLACE ROD CONTROL

IN MANUAL. /

9 8 Before adjustment of GAIN Verifies Feed Reg

potentiometer for N-44, the Bypass Valve

Feed Reg Bypass Valve Controllers are already

Controllers should be placed in Manual position

in manual to prevent

undesired valve motion

during adjustment

10 9 If a RATE TRIP signal Resets any Rate Trip

occurs, before going to the signals generated before

next channel, reset the RATE completing task for

TRIP signal. channel N-44

  • 11 10 At each power range Unlocks and slowly Critical to establish

drawer B, unlock and adjusts Gain pot in proper indication

slowly adjust GAIN CW direction until and operation of

potentiometer until the indicated power is channel N-44

indicated power is within within 0.2% of value

0.2% of the DESIRED IND previously determined

from Step 3 in Step 3 (JPM Step 4)

12 1I If there is insufficient fine N/A's step since

gain adjustment using the adequate adjustment

drawer B gain potentiometer, exists

perform the following:

Page 5 of 7

JPM SRO-B. l.g

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

Na STEP STEP UNSA

13 12 Lock GAIN potentiometer in Locks Gain pot on N-44

place in place

14 Independent verification is Requests independent

required verification

CUE: FOR PURPOSES OF THIS 3PM ONLY,

INDEPENDENT VERIFICATION WILL NOT BE

PERFORMED.

15 13 Record the as left GAIN Records as left Gain pot

potentiometer setting setting (within + 0.02 of

actual)

SC2 5

16 14 On Drawer A, place the Places Meter Rate

METER RATE switch in switch in Slow position

SLOW.

17 Independent verification is Requests independent

required verification

CUE: FOR PURPOSES OF THIS JPM ONLY,

INDEPENDENT VERIFICATION WILL NOT BE

PERFORMED.

18 15 Record the new indicated Records the new N-44

______ power (on drawer A)

Verify that new indicated

indicated power

Verifies that N-44

9

Critical since 2% is

_

"*19 16

power is within 2% of indicated power is limit for performing

desired indication from within 2% of desired gain adjustment

Step 3 above, indication

20 17 Place ROD BANK Places Rod Control back

SELECTOR switch in the in automatic

desired position

21 18 Place Feed Reg Bypass Valve Leaves Feed Reg Bypass

Controllers in the desired Valves in manual

position

TASK COMPLETE

STOP TIME:

Page 6 of 7

Attachment 2

Sheet I of 6

Power Range NI Gain Adjustment

Person(s) Performing Checklist:

Initials Name (Print) Initials Name (Print)

Remarks- Indicate any component not in the prescribed position.

Checklist Started Time Date

Checklist Completed Time Date

Approved by

Unit SCO Date

After receiving the final review signature, this OP Attachment becomes a QA RECORD and should be

submitted to Document Services.

OP-105 Rev. 15 Page 38 of 44

Attachment 2

Sheet 2 of 6

Power Ranae NI Gain Adiustment

1. Record the as found setting of the GAIN potentiometer on the front of Power Range Drawer B.

N42 N)N -N1 N43 0 L

N41 N A N44

NOTE: Calculated power shall be that power calculated by OST1000, OST-1004 or other

applicable plant procedures.

CAUTION

To prevent a possible norconservative adjustment being made, no significant power decreases should

be made between the time of performance of the calorimetric and the following adjustments.

2. Determine the difference, including sign, between the calculated power and the indicated reactor

power at the time data was obtained as follows:

CALC PWR N41 IND PWR N41 DIFFERENCE

0NS

4

CALC PWR N42 DIFFERENCE

N42 IND PWR

ACN W N43 DIFFERENCE

CALC PWR N43 IND PWR

N44 DIFFERENCE

CALC PWR N44 IND PWR

OP-105 Rev. 15 Page 39 of 44

Attachment 2

Sheet 3 of 6

3. Determine the desired indication, including sign, of NIS as follows:

+

N41 PRESENT IND N41 DIFFERENCE N41 DESIRED IND

NP* +

N42 PRESENT IND N42 DIFFERENCE N42 DESIRED IND

+ N F =

N43 DIFFERENCE N43 DESIRED IND

N43 PRESENT IND

+

N44 DIFFERENCE N44 DESIRED IND

N44 PRESENT IND

4. Calculation in Steps 2 and 3 independently verified.

CAUTION

Adjustments should not be made toone Power Range channel whileanotherchannel has tripped

bistables. This may cause a reactor trip due to required logic being completed. (Ref. CR 903027-5)

5. Before each channel adjustment, verify that there arE.o PR trip bistables energized on TSLB3

or TSLB-4, except for trip bistables that are manually blocked. (Channels not being adjusted may

be marked N/A)

N41 0A N42 t N43 ,,__ N44

OP-105 Rev. 15 Page40 of 44

Attachment 2

Sheet 4 of 6

NOTE: After the GAIN adjustment, the METER RATE switch may be returned to

SLOW to evaluate if the adjustment is adequate.

6. On Drawer A, place the METER RATE switch in FAST.

N4

N42 NA-

  • N43 K,A N44

N41 N pt

7. Before adjustment of GAIN potentiometer for N44, the ROD BANK SELECTOR switch should be

placed in MANUAL to prevent undesired rod movement during the adjustment.

8. Before adjustment of GAIN potentiometer for N4$4, the Feed Reg Bypass Valve Controllers

should be placed in manual to prevent undesired valve motion during adjustment.

9. If a RATE TRIP signal occurs, before going to the next channel, reset the RATE TRIP signal.

(Otherwise N/A)

CAUTION

Adjustment of GAIN potentiometer should be made slowly to avoid producing a RATE TRIP signal.

10. At each power range drawer B, unlock and slowly adjust GAIN potentiometer until the indicated

power is within 0.2% of the DESIRED IND from Step 3.

0P-1 05 Rev. 15 Page4l of 44

Attachment 2

Sheet 5 of 6

11. Ifthere is insufficient fine gain adjustment using the drawer B gain potentiometer, perform the

following: (Sign off space should be initialed after completion of all NI adjustments), (Step is N/A

if coarse gain adjustment is not performed)

NOTE: Substeps a and b may need to be done simultaneously to prevent reaching the 103% Rod

Stop.

a. On the front of Power Range drawer B, set the GAIN potentiometer to 5.

b. Open the Power Range drawer B, unlock and adjust the Coarse Level Adjust

potentiometer (R312) (located on the lower right rear on the base plate) until indicated

power is within 0.5% of the DESIRED IND from StelS.

c. Record the Coarse Level Adjust setting.

N41 *_.2A N42 NJ t- N43 0fl N44

d. Lock the Coarse Level Adjust potentiometer (R312).

-S

3

N41 0 / N42 t /

Position/Verify PositionNerify

N43 0 / PR N44 I

Position/verify Position/Verify

e. Continue with Step 10 above.

OP-105 Rev. 15 Page42 of 44

Attachment 2

Sheet 6 of 6

12. Lock GAIN potentiometer(s) in place. Independent verifistion is required.

4.

N41 0 / Pr N42 N\ / A,

Position/Verify Position/Verify

N43 ,M/t'

N44 /

Position/Verify PositionNerify

13. Record the as left GAIN potentiometer setting(s):

N41 t ý N42 i Pt' N43 -A) N44

14. On Drawer A, place the METER RATE switch in SLOW.

N41 3

t-/ i k N42 t__/ N

Position/Verify PositionNerify

N43 Q3 / N 0'

N44 /

Position/Verify Position/Verify

15. Record the new indicated power (on drawer A)

N43 ,N No

N41 t3 , N42 Nt, N44

16. Verify that new indicated power is within 2% of desired indication from Step above. Initial in

appropriate space(s).

N41 t-' N42 Nk 9" N43 *-)P N44

17. Place ROD BANK SELECTOR switch in the desired position.

18. Place Feed Reg Bypass Valve Controllers in the desired position.

0P-1 05 Rev. 15 Page43 of 44

JPM SRO-B. lIg

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is at 100% equilibrium conditions.

Following maintenance on PR Channel N-44, all required testing has been completed

and the channel is ready to be returned to service. A calorimetric hasjust been

performed per OST-1004, "Power Range Heat Balance, Computer Calculation, Daily

Interval, Mode 1 (Above 15% Power)."

The calculated power is 99.8%. Indicated power on PR channel N-44 at the time of

the calorimetric was at its current value. Rod Control is in Automatic.

INITIATING CUE(S):

You are to perform the Power Range NI Gain Adjust for PR channel N-44 in

accordance with OP- 105, "Excore Nuclear Instrumentation," Section 8.3 and

Attachment 2.

Page 7 of 7

JPM COM-B.2.a

HARRIS

/

K /

S/

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM COM-B.2.a

Local Actions for a Dropped Rod Recovery

-I

CANDIDATE:

EXAMINER:

Page I of 8

JPM COM-B.2.a

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Local Actions for a Dropped Rod Recovery

ALTERNATE PATH: None

FACILITY JPM NUMBER: IP-153

KA: 003AA1.02 IMPORTANCE: SRO 2.9 RO 2.9

KA STATEMENT: Operate the demand position counter and pulse/analog

converter

TASK STANDARD: Local actions have been completed for rod recovery

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT ,'

PREFERRED EVALUATION METHOD: PERFORM SIMULATE '

REFERENCES: AOP-001, Malfunction of Rod Control and Indication System

VALIDATION TIME: 15 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

JPM COM-B.2.a

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

"Keys33-36

AOP-001, "Malfunction of Rod Control and Indication System"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All in plant

steps shall be performed for this JPM, including any required communications. DO

NOT operate any equipment without my permission. I will provide initiating cues and

reports on other actions when directed or asked by you. Ensure you indicate to me

when you understand your assigned task. To indicate that you have completed your

assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

The plant was at 50% power when control bank D rod H2 dropped to the bottom of the

core.

Plant conditions have stabilized and the problem with rod H2 is fixed.

The crew is ready to retrieve the dropped rod.

INITIATING CUE(S):

Rod H2 is ready to be retrieved.

The SCO has directed you to obtain the correct key(s) and perform the local actions

associated with the retrieval of the dropped rod in accordance with AOP-00 1,

"Malfunction of Rod Control and Indication System," Section 3.1.

Page 3 of 8

JPM COM-B.2.a

HARRIS

START TIME:

  • DENOTES CRITICAL STEP

I

ELEMENT STANDARD NOTES SAT/

JPSJM PROC

STEFP STEP UNSAT

I I _________________________________________________________ __________

NA Obtain copy of procedure Obtains current copy of

AOP-001, Section 3.1

CUE: THE CONTROL ROOM INFORMS YOU

It,,

THEY ARE READY FOR YOU TO PERFORM

STEPS 3.1.12, 3.1.13, AND 3.1.14.

3.1.12 Obtain the key for the Control Obtains keys 33-36

Rod Disconnect Switch Box

(keys 33-36),,,-

  • 3 3.1.13 Position lift coil disconnect * Unlocks cabinet Only critical to open

and places the disconnect switches

switches for rods in the for affect rods

affected bank as follows: disconnect switches

"* Dropped rod - ROD for CBD group 1

rods B8, H14, and Critical to ensure

CONNECTED (down) only rod H2 moves

P8 and group 2

"* All other rods - ROD during retrieval

rods F6, F1O, K10,

DISCONNECTED (up)

and K6 in the up

position

"* Ensures rod H2 in

CBD group I is in

the down position

"* Notifies Control

Room of disconnect

switch alignment

CUE: THE DISCONNECT SWITCHES FOR CBD

GROUP 1 RODS B8, H14, AND P8, AND FOR

GROUP 2 RODS F6, FlO, K10, AND K6 ARE IN

THE UP POSITION. THE DISCONNECT SWITCH

FOR CBD ROD H2 IS IN THE DOWN POSITION.

Page 4 of 8

JPM COM-B.2.a

HARRIS

PROC ELEMENT STANDARD NOTES SAT/

JPM

STEP UNSAT

STEP

  • 4 3.1.14 Record the Pulse-To "* Opens the P/A Only critical to

converter cabinet, record P/A reading

Analog (P/A) converter

reading for the affected selects Control

Bank D, and Critical to ensure

bank: proper response

"* Bank records the reading

for Control Bank D after resetting P/A

"* P/A Reading converter later

"* Informs Control

Room that Steps

3.1.12, 3.1.13, and

3.1.14 are complete

CUE: CONTROL BANK D HAS BEENSELECTED

AND THE INDICATION IS 165.

CUE: THE CONTROL INFORMS YOU THAT ROD

ARE TO

H2 HAS BEEN RETRIEVED AND YOU

PERFORM STEPS 3.1.23 AND 3.1.24.

  • 5 3.1.23 Repeatedly Press the Depresses tthe Master Only critical to

Cycler +1 button until ensure Master

"Master Cycler +1" button Cycler light display

as needed to produce the the light status on Card

A105 is: is correct

following light status on

Card A105: "* Top light- LIT

"* Middle light - NOT Critical to ensure

"* Top light - LIT proper response of

"* Middle light - NOT LIT LIT

rod control system

"* Bottom light - LIT "* Bottom light - LIT

following

"* Informs Control completion of rod

Room that Master

retrieval

Cycler indicates

correctly

CUE: THE LIGHT STATUS ON CARD A105 IS

THE TOP AND BOTTOM LIGHTS ARE LIT AND

THE MIDDLE LIGHT IS NOT LIT.

Page 5 of 8

JPM COM-B.2.a

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT

  • 6 3.1.24 Close all lift coil disconnect * Places the Only critical to

switches opened in step 13. disconnect switches connect disconnect

for CBD group I switches

rods B8, H14, and

P8 and group 2 Critical to ensure

rods F6, F10, K10, movement of rods

and K6 in the down following

position completion of rod

  • Closes and locks retrieval

cabinet

\ Room that

disconnect switches

are in connect

position

-CUE: ALL DISCONNECT SWITCHES ARE IN

THE DOWN POSITION.

CUE: THE CONTROL INFORMS YOU THAT ROD

H2 HAS BEEN RETRIEVED ANDYOU ARE TO

PERFORM THE RNO STEPS OF STEP 3.1.26.

  • 7 3.1.26. Perform the following at the Positions the Bank Critical to ensure

a Pulse-To-Analog (P/A) Display Selector Switch proper operation of

(RNO) Converter: to the Bank D position P/A converter and

  • Position the Bank rod insertion limit

Display Selector Switch monitor

to the bank recorded in

step 14

CUE: BANK DISPLAY SELECTOR SWITCH IS IN

THE BAN1Jjq!OSITION.

  • 8 3.1.26. e Position and Hold the Positions and Holds the Critical to ensure

b Auto-Manual switch in Auto-Manual switch in proper operation of

(RNO) MANUAL MANUAL P/A converter and

rod insertion limit

monitor

SWITCH IS BEING HELD

CUE: AUTO-MANUAL

IN THE MANUAL POSITION.

Page 6 of 8

JPM COM-B.2.a

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT

  • 9 3.1.26. * Repeatedly Press either Depresses UP Critical to enlsure

pushbutton until P/A proper operation of

C the UP pushbutton or

reading indicates 165 P/A converter and

the DOWN pushbutton

rod insertion limit

as needed to make the

monitor

display match the P/A

reading recorded in step

14

I I. T

I I

CUE: BEFORE DEPRESSING THE UP3 :5 (

PUSHBUTTON, THE P/A READING IS 163 STEPS.

CUE: AFTER DEPRESSING THEtUP , ,

PUSHBUTTON, THE P/A READING IS 165 STEPS.

10 3.1.26. * Release the Auto-Manual Releases Auto-Manual

d switch switch

(RNO)

CUE: THE AUTO-MANUAL SWITCH HAS BEEN

RELEASED.

3.1.26. * Position the Bank Display * Positions Bank

e Selector Switch to Display Selector

(RNO) DISPLAY OFF Switch to DISPLAY

OFF and closes

cabinet

  • Informs Control

Room that RNO

steps of Step 3.1.26

are complete

CUE: BANK DISPLAY SELECTOR SWITCH IS IN

THE DISPLAY OFF POSITION.

TASK COMPLETE

STOP TIME:

Page 7 of 8

JPM COM-B.2.b

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM COM-B.2.b

Manually Control Charging Due to a Loss of IA

CANDIDATE:

EXAMINER:

Page I of 6

JPM COM-B.2.b

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Manually Control Charging Due to a Loss of IA

ALTERNATE PATH: None

FACILITY JPM NUMBER: IP-084

KA: 004.A2.11 IMPORTANCE: SRO 4.2 RO 3.6

KA STATEMENT: Correct, control, or mitigate the consequences on CVCS

caused by the following malfunction: Loss of IAS

TASK STANDARD: Charging flow is being controlled locally

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT

PREFERRED EVALUATION METHOD: PERFORM SIMULATE

REFERENCES: AOP-0 17, Loss of Instrument Air

VALIDATION TIME: 10 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 6

JPM COM-B.2.b

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

AOP-0 17, "Loss of Instrument Air"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All in plant

steps shall be performed for this JPM, including any required communications. DO

NOT operate any equipment without my permission. I will provide initiating cues and

reports on other actions when directed or asked by you. Ensure you indicate to me

when you understand your assigned task. To indicate that you have completed your

assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

The plant is at 100 percent power.

An instrument air header has ruptured on the RAB 236-foot elevation. The header has

been isolated but FCV- 122, Charging Flow Control Valve, has failed open.

The Control Room has isolated charging (1CS-235 and 238 are shut). Pressurizer

level is 55 percent.

INITIATING CUE(S):

You have been directed to locally control charging flow per AOP-0 17, "Loss of

Instrument Air," Section 3.1, Step 6.b (RNO).

Page 3 of 6

JPM COM-B.2.b

HARRIS

">--- START TIME:

  • DENOTES CRITICAL STEP

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT

I NA Obtain copy of procedure current copy of

'Obtains

AOP-017, Section 3.1

2 6.b.(1) Locally control charging flow Contacts Control Room

(RNO) by shutting at least one of the and requests ICS-235

following: and/or be closed ICS

1ICS-235, Charging Line 238

Isolation

  • ICS-238, Charging Line

Isolation

CUE: CONTROL ROOM REPORTS BOTH ICS

235 AND ICS-238 ARE CLOSED (ALSO GIVEN ON

INITIATING CUE).

  • 3 6.b.(2) Locally shut 1CS-228, * Rotates valve Critical to isolate

(RNO) Charging Line FCV Inlet handwheel in CW failed open FCV

Isolation Valve direction until no 122 to allow control

further movement of charging flow

is obtained

  • Informs Control

Room that 1CS-228

is closed

CUE: HANDWHEEL FOR 1CS-228 HAS BEEN

ROTATED IN CW DIRECTION AND NO

FURTHER MOVEMENT CAN BE OBTAINED.

  • 4 6.b.(3) Verify open the following: Contacts Control Critical to ensure

(RNO) e 1CS-235, Charging Line Room and requests the both valves are open

Isolation following valves both to allow charging

0 1CS-238, Charging Line be opened: flow to RCS

Isolation * 1CS-235

  • ICS-238

CUE: CONTROL ROOM REPORTS BOTH ICS

235 AND lCS-238 ARE OPEN.

Page 4 of 6

JPM COM-B.2.b

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP I I

UNSAT

  • 5 6.b.(4) (CONTINUOUS ACTION) Throttles open ICS- Critical to provide

(RNO) Locally throttle ICS-227, 227 by rotating required charging

Norm Charging Line FCV handwheel in CCW flow to RCS

Bypass, to obtain desired direction until directed

charging flow to stop opening by

Control Room

CUE: HANDWHEEL FOR 1CS-227 IS BEING

ROTATED IN CCW DIRECTION. CONTROL

ROOM DIRECTS YOU TO STOP OPENING

VALVE AND MAINTAIN CURRENT POSITION.

6 6.b.(4) Maintain current position of * Stops opening ICS

(RNO) ICS-227, Norm Charging 227 when directed

Line FCV Bypass by Control Room

0 Informs Control

Room that I CS-227

is being throttled to

required position

TASK COMPLETE

STOP TIME:

Page 5 of 6

JPM COM-B.2.b

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is at 100 percent power.

An instrument air header has ruptured on the RAB 236-foot elevation. The header has

been isolated but FCV- 122, Charging Flow Control Valve, has failed open.

The Control Room has isolated charging (ICS-235 and 238 are shut). Pressurizer

level is 55 percent.

INITIATING CUE(S):

You have been directed to locally control charging flow per AOP-0 17, "Loss of

Instrument Air," Section 3.1, Step 6.b (RNO).

Page 6 of 6

JPM COM-B.2.e

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

JPM COM-B.2.c

Start Up a Hydrogen Recombiner

CANDIDATE:

EXAMINER:

Page 1 of 8

JPM COM-B.2.c

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JOB PERFORMANCE MEASURE

TASK: Start Up a Hydrogen Recombiner

ALTERNATE PATH: None

FACILITY JPM NUMBER: IP-020

KA: 028A4.01 IMPORTANCE: SRO 4.0 RO 4.0

KA STATEMENT: Operate the Hydrogen Recombiner controls

TASK STANDARD: Electric Hydrogen Recombiner B is in operation with the

proper power setting

PREFERRED EVALUATION LOCATION: SIMULATOR IN PLANT YO

PERFORM SIMULATE v'

PREFERRED EVALUATION METHOD:

REFERENCES: OP- 125, Post Accident Hydrogen System

VALIDATION TIME: 20 MINUTES TIME CRITICAL: No

CANDIDATE:

START TIME: FINISH TIME:

PERFORMANCE TIME: MINUTES

PERFORMANCE RATING: SAT UNSAT

COMMENTS:

EXAMINER:

Signature Date

Page 2 of 8

JPM COM-B.2.c

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

OP-125, "Post Accident Hydrogen System"

READ TO OPERATOR C

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All in plant

steps shall be performed for this JPM, including any required communications. DO

NOT operate any equipment without my permission. I will provide initiating cues and

reports on other actions when directed or asked by you. Ensure you indicate to me

when you understand your assigned task. To indicate that you have completed your

assigned task, return the handout sheet I provide you.

INITIAL CONDITIONS:

The plant has sustained a LOCA.

RCS pressure is 350 psig and core exit T/Cs are > 1200°F.

INITIATING CUE(S):

EPP-FRP-C. 1, "Response to Inadequate Core Cooling," directs starting up a hydrogen

recombiner.

The Unit SCO directs you to start up Electrical Hydrogen Recombiner B using OP

125, "Post Accident Hydrogen System," Section 5.1.

Page 3 of 8

JPM COM-B.2.c

HARRIS

START TIME:

  • DENOTES CRITICAL STEP

PROC ELEMENT STANDARD NOTES SAT/

JPM

UNSAT

STEP STEP

I Obtains current copy of

NA Obtain copy of procedure

OP-125, Section 5.1

CUE: INITIAL CONDITIONS FOR SECTION 5.1

ARE COMPLETED.

2 5.1.2.1.a Perform the following Refers to SPTOP or

calculation: MCB containment

"* Measure the contain- pressure indications to

ment pressure after a determine containment

LOCA using one of the pressure

following:

"* SPTOP

"* PI-950 SA, PI-952

SA, PI-951 SB, PI

953 SB

CUE: CONTAINMENT PRESSURE IS SIG.

3 5.1.2.1.b " Determine the pre- Refers to DSR OST

LOCA containment 1021 to determine last

temperature from OST- known containment

1021 records temperature prior to

LOCA

CUE: PRE-LOCA CONTAINMENT

4 5.1.2.1.c *Determine Pressure Refers te SAttachment 8

FH~TEMPERATURE Factor (Cp) WAS

from 90°F. of OP- 12e5 and

etAttachment 8. determin aes Cp value of

1.29 (1.228 to 1.30)

Page 4 of 8

JPM COM-B.2.c

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

  • 5 5.1.2.1.d * Calculate required Refers to Attachment 8 Critical to

Electric Hydrogen of OP-125 and determine value to

Recombiner (EHR) calculates ERR power set EHR final

power by multiplying to be 51.91 KW (51.51 setting

Cp x Reference Power to 52.31)

as shown on Attach NOTE: Using

ment 8. values for EHR A

in error will result

in range of 52.84 to

53.67

6 5.1.2.2.a At the EHR Control Panel Verifies Power In

B-SB, perform the Available white light is

following: lit

Verify lit, Power In

Available, white light

CUE: 'POWER IN AVAILABLE' WHITE LIGHT

IS LIT.

7 5.1.2.2.b * Set the Power Adjust Rotates Power Adjust

potentiometer at zero pot fully CCW to zero

(000).

CUE: 'POWER ADJUST' POT HAS BEEN

ROTATED FULLY TO ZERO POSITION.

  • 8 5.1.2.2.c * Place the Power Out Places Power Out Critical to provide

switch to on switch to on position output from EHR

CUE: 'POWER OUT' SWITCH IS IN ON

POSITION.

9 5.1.2.2.d * Verify lit the red light on Verifies red light lit on

the switch plate switch plate

CUE: RED LIGHT ON SWITCH PLATE IS LIT.

Page 5 of 8

JPM COM-B,2.c

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT /

STEP STEP UNSAT

10 5.1.2.2.1 Turn the Power Adjust Rotates Power Adjust

potentiometer clockwise pot CW until Power Out

until 5 KW is obtained Meter indicates 5 KW

on the Power Out meter.

CUE: 'POWER ADJUST' POT HAS BEEN

ROTATED IN CW DIRECTION AND 'POWER

OUT' METER READS 5 KW.

11 5.1.2.2.g Maintain 5 KW for 10 Maintains current

minutes. position on Power

Adjust pot for 10

minutes

CUE: 10 MINUTES HAVE ELAPSED.

12 5.1.2.2.h Turn the Power Adjust Rotates Power Adjust

potentiometer clockwise pot CW until Power Out

until 10 KW is obtained Meter indicates 10 KW

on the Power Out meter

CUE: 'POWER ADJUST' POT HAS BEEN

ROTATED IN CW DIRECTION AND 'POWER

OUT' METER READS 10 KW.

13 5.1.2.2.i Maintain 10 KW for 10 Maintains current

minutes. position on Power

Adjust pot for 10

minutes

CUE: 10 MINUTES HAVE ELAPSED.

14 5.1.2.2.j Turn the Power Adjust Rotates Power Adjust

potentiometer clockwise pot CW until Power Out

until 20 KW is obtained Meter indicates 20 KW

on the Power Out meter.

CUE: 'POWER ADJUST' POT HAS BEEN

ROTATED IN CW DIRECTION AND 'POWER

OUT' METER READS 20 KW.

Page 6 of 8

JPM COM-B.2.c

HARRIS

JPM PROC ELEMENT STANDARD NOTES SAT/

STEP STEP UNSAT

15 51.2.2.k * Maintain 20 KW for 5 Maintains current

minutes. position on Power

Adjust pot for 5 minutes

CUE: 5 MINUTES HAVE ELAPSED.

  • 16 5.1.2.2.1 * Turn the Power Adjust Rotates Power Adjust Critical to establish

potentiometer pot CW until Power proper power

clockwise until the Out Meter indicates output from EHR

required power setting 51.51 to 52.31 KW

calculated in Step (Value determined in

5.1.2.1.d (JPM Step 5) JPM Step 5)

is obtained on the 60.3

Power Out meter.

CUE: 'POWER ADJUST' POT HAS BEEN

ROTATED IN CW DIRECTION AND 'POWER

OUT' METER READS 51.51 to 52.31 KW (Value

determined in JPM Step 5).

TASK COMPLETE

STOP TIME:

Page 7 of 8

JPM COM-B.2.c

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant has sustained a LOCA.

RCS pressure is 350 psig and core exit T/Cs are > 1200 0 F.

INITIATING CUE(S):

EPP-FRP-C. I, "Response to Inadequate Core Cooling," directs starting up a hydrogen

recombiner.

The Unit SCO directs you to start up Electrical Hydrogen Recombiner B using OP

125, "Post Accident Hydrogen System," Section 5.1.

Page 8 of 8

PowerTrax Operating Strategy Generator Module 5 mw/min back down

Today's Date

52 EFPDH

Step Date Time Power ppm B Gal Gal R Step AFD AO- XE Worth

Bor Dil XE

01 fl -

1 0000 100 Ill/ 814 0 nA~1 2589

92 1187 72 210

2 0015 0 2598

84 1196 75 205

3 0030 0 2613

76 1205 79 199

4 0045 0 2644

68 1209 24 195

5 0100 0 2683

60 1215 36 190

6 0115 0 2724

52 1220 29 180

7 0130 0 2769

44 1225 45 170

8 0145 0 2819

38 1230 0 149

9 0200 0 2878

30 1230 0 140

10 0215 0 2943

22 1230 0 128

11 0230 0 3025

14 1230 0 116

12 0 3134

6 1230 0 0 100

13 0300

14

15

16

17

Attachment 6

Sheet 1 of 3

SI Accumulator Samiple Recuired Reference Levels

INSTRUCTIONS

NOTE: An SI Accumulator boron sample is not required when the volume

increase makeup source is the Refueling Water Storage Tank (RWST)

and the RWST has not been diluted since verifying that the RWST

boron concentration is equal to or greater than the Accumulator

boron concentration limit. (Ref. T.S. 3.5.1)

The Sample Required Reference Level is an aid to determine if Tech

Spec event driven surveillance sampling of an Accumulator is

required due to a level increase of 9% or more from a source other

than the RWST at its required boron concentration. The Sample

Required Reference Level is the Accumulator level at the time the

last sample was drawn plus an additional 9%. This value must be

adjusted for any decreases in Accumulator level since the last

sample. This value must also be adjusted for any increase in

Accumulator level due to makeup from the undiluted RWST since the

last sample. The Sample Required Reference Level is calculated and

adjusted per this Attachment. This ensures that any cumulative

level increase of greater than or equal to 9%, from a source other

than the undiluted RWST, will be detected.

Any step that does not apply should be marked N/A.

Current Required Reference Levels are maintained on the Status

Board and in the RO narrative log.

new

1. Update the Sample Required Reference Level on TABLE 1 for any

samples and record on status board and in the RO narrative log.

2. Verify all calculations in TABLE 1.

the

3. Update the Sample Required Reference Level on TABLE 2 for any of

and in the RO narrative log:

following and record on staus board

Decrease in level due to draining or temperature changes.

Increase in level due to makeup to Accumulators from undiluted

RWST.

4. Verify all calculations in TABLE 2.

Level in

5. Enter details of any changes to the Sample Required Reference

the Comments section of the respective TABLE.

Rev. 44 Page 32 of 36

OST-1021

Attachment 6

Sheet 2 of 3

SI Accumulator Samole Repcaired Reference Levels (continued)

TABLE 1:

Accumulator Reference Level initial calculation after sampling. After 2400

hours N/A any blank spaces. If multiple samples per Accumulator are required,

attach other sheets (Attachment 6 sheet 2).

Time of Level at the time of the Level increase Sample Required Performed by

Accum Sample last sample + requiring - Reference Level

additional

nit Verify

sampling (9%)

LI-920 9%

A

LI-922 9%

LI-924 9%

B

LI-926 9%

LI-928 9  %

LI-930 9%

Comments:

OST-1021 Rev. 44 Page 33 of 36

Attachment 6

Sheet 3 of 3

SI Accumulator Sample Reauired Reference Levels (continued)

TABLE 2:

Accumulator Reference Level Adjustments for level changes due to draining an Accumulator, or decrease due to

Containment temperature effects, or level increase from the RWST with RWST verified within Accumulator boron

limits. After 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />, N/A any blank spaces. If multiple entries per Accumulator are required, attach

other sheets (Attachment 6 sheet 3).

Previous Sample New Sample Performed by

Accum Time Required Reference -" Finel Level iLevel Level = Required

Level Reference Level Init Verify

LI-920

A

LI-922 -

B

LI-924 ......... , ....

LI-926

LI-928

C

LI-930

Comments:

OST-1021 Rev. 44 Page 34 of 36

5.1.8 Instrument Reading and Control Indications

R 1. The Unit SCO and Control Operators have authority and

responsibility to limit plant operations, or to shut down the plant

when warranted by plant conditions, unusual circumstances or

unexplained events. Such actions may be warranted on the basis of

instrument readings or control indications not consistent with

expected plant responses. When analyzing such situations, shift

operating personnel must consider instrument readings and control

indications to be true unless readings are proven to be incorrect.

(Reference 2.4.0.0.3)

2. Operations personnel will not make changes to RPS or ESFAS

setpoints that are not specifically directed by approved Plant

Operating Manual procedures. (Reference 2.3.0.0.5 and 2.3.0.0.6)

3. Control board indication(s) affected by the performance of approved

tests or a clearance should have a colored marker placed on or next

to the indicator. The test/clearance number may be written on the

marker for reference. Coding Annunciators will be per Section

5.1.13.

5.1.9 Maximum Acceptable Deviation Between Redundant Indicators and Recorders

1. Many important process variables are redundantly sensed, processed,

transmitted, indicated and recorded. Many redundant transmitters

also provide signals to Reactor Protection and Safeguards Logic

Systems to assure that single failures do not cause nor prevent

safety function initiation. It is extremely important that the

performance of instrumentation systems be carefully monitored to

quickly identify instrument malfunctions which could show a loss of

or non-conservative operation of Reactor Protection or Safeguards

System actuation.

2. while the guidance specified here primarily applies to

instrumentation requiring channel checks per Tech Specs, the

Operating staff must also be alert to other instruments which could

be indicating improperly. This may be based on known plant

conditions and prompt corrective actions must be initiated to

correct such situations.

3. Redundant safety significant indicators are checked per Tech Spec

Daily Surveillance Requirements (DSR). Checks are made to

determine deviations between the highest and lowest indication of

redundant indicators for the same parameter with the same scale. A

deviation greater than 5% of full range of movement is

unacceptable. Also, any instrument pegged below zero, when it is

known that the instrument should not be pegged low by design, is

unacceptable. The following are examples of instruments with

greater than 5% range of movement:

For steam flow loops, if power is less than or equal to 19%

rated thermal power, then steam flow should be greater than

90% of indicated feed flow AND the tolerance between

redundant steam flow channels should be within 11% of full

scale. If it appears that the 5% tolerance will not be met

before exceeding 19% turbine load, then the Responsible

Engineer should be contacted to evaluate the specific

situation.

OMM-001 Rev. 49 Page 30 of 88

5.1.9 Maximum Acceptable Deviation Between Redundant Indicators and Recorders

(continued)

When channel checking the Main Feedwater Flow Transmitters

between 10% and 5% Rated Thermal Power the maximum difference

between channels should be less than or equal to 350 KPPH.

Below 5% Rated Thermal Power the maximum difference between

channels should be less than or equal to 500 KPPH.

(Reference ESR 9500910)

For the Auxiliary Feedwater Flow Transmitters a channel check

is performed with flow isolated. At zero actual AFW flow,

the transmitter output could be as high as 23.8 KPPH or as

low as (-)23.8 KPPH and still be in calibration. The channel

should be considered Operable when the indication is within

this band and the pointer is not resting on the lower stop of

tbs indicator. The pointer can be verified not resting on

the lower stop by tapping the indicator to determine the

position of the stop. (Reference ESR 96-00060)

R During shutdown operations, the source range NIs provide

continuous indication of core subcriticality except during

periods of required testing, or core off-load. The source

range NIs are utilized to mitigate the effects of a boron

dilution accident that occurs when the reactor is

subcritical. Electromagnetic interference (EMI) affecting

both channels or interference causing excessive count rate

indication by a factor of ten (one decade) or greater are not

acceptable. EMI from identifiable maintenance activities,

such as welding, is not considered a functional failure.

To determine operability during shutdown conditions perform

and verify the following calculation: (Reference ESR 9600179)

LOG (Highest SR NI) - LOG (Lowest SR NI) * 1.0

The difference between individual channels shall not exceed

50,000 counts per second. (Reference FSAR table 7.5.1-14)

The audible function of the Source Range monitors should be

verified Operable per Tech Spec 3.9.2 during Mode 6 as part

of the channel check of the Source Range instruments.

When a NFMS monitor N-60 or N-61 is being used as a

replacement Source Range monitor to satisfy T.S. 3.9.2,

acceptable channel check criteria to calculate and verify is

as follows: (Comparison of SR with the replacement NFMS)

LOG (Highest SR(NFMS) - LOG (lowest SR(NFMS) * 2.0*

  • This value may be increased to 3.0 if the NFMS value is

less than 1 cps.

FI-O1AV-4842ASA and FI-01AV-4842BSB, RAB Emergency Exhaust

A(B) Flow Indicators, with no actual flow may indicate as

high as 700 cfm or be pegged low and still be within

calibration.

OMM-001 Rev. 49 Page 31 of 88

5.1.9 Maximum Acceptable Deviation Between Redundant Indicators and Recorders

(continued)

4. The 5% guidance applies only to the MCB and ACP instrumentation.

It is in no way intended to apply to instrumentation of different

types sensing the same parameter, that is, a direct reading local

pressure gauge versus a pressure transmitter driving a remote

meter. The channel most likely to be out of tolerance is the

channel with the greatest deviation from the remaining channels.

If only two channels indicate the same parameter, judgement based

on known conditions and past performance of the channels in

question must be used to determine which channel is out of

tolerance.

5. Once an unacceptable deviation is identified, corrective action

consistent with the Plant Technical Specifications, and Operations

Work Procedures (OWP) should be started.

6. Place a yellow sticker next to the respective MCB and ACP

instrument per Section 5.1.22, as a visual reminder to the operator

that an unacceptable deviation has been identified, per AP-38,

Deficiency Tag Procedure.

7. The following provides a guide for initiating a work request:

a. Declare the channel inoperable and insert the appropriate

trips to maintain the minimum degree of redundancy. Initiate

a work request.

OR

b. Declare the channel to be deviating by a known constant

amount. If the deviation is in a conservative direction, an

appropriate trip need not be inserted. If the deviation is

in a non-conservative direction, insert the appropriate trips

to maintain minimum degree of redundancy. Initiate a work

request.

8. Any trips inserted may be reset after the protection portion of the

channel is verified to be operating properly and declared operable.

When an instrument is returned to normal status, remove the yellow

marker from the MCB and ACP per Section 5.1.22.

5.1.10 Housekeeping

1. The Control Room is to be maintained in a clean, orderly condition

to assure safe, efficient operations. Shift Personnel are

responsible for Control Room upkeep.

NOTE: It is sometimes advisable not to clean or dust in some areas of the

Control Room during plant operations. This is because of the potential

hazards associated with bumping or otherwise moving critical controls.

2. Shift operating personnel will perform cleaning of control

consoles, instrument panels and computer consoles and the orderly

storage of books, drawings and records.

3. All areas assigned to Operations will be kept in a neat and orderly

manner.

OMM-001 Rev. 49 Page 32 of 88