ML022690438
ML022690438 | |
Person / Time | |
---|---|
Site: | Harris |
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
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
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
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
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
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
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
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
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
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,
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
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.
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
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.
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
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 _______ _______
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)
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
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
TRC0412D TRC0422D TRC0432D Normally 3) TAVG
TI-412D TI-422D TI-432D
e(# Operable
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
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.
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
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
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
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
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
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.
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
1ý
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.
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
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
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
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
TASK: Determine Rod Misalignment Using Thermocouples
ALTERNATE PATH: None
FACILITY JPM NUMBER: NEW
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"
- Thermocouples abandoned by EC 47997
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)
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
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
TASK: Perform a Manual Power Range Heat Balance Calculation
ALTERNATE PATH: None
FACILITY JPM NUMBER: NEW
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
- 2 AXtit. -5 Calculate Steam Generator accurately
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/
UNSAT
STEP STEP
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
- 6 1 Alt. 5 - 4 Steam Generator Powers accurately
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
SG A Avq Transmiltter Sig/w
4.076 ___ _ " ; 2. 777A
4.062
v 7p
Val ts
FTy'rOC A VOxts F 2ý0A V*lV:
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
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
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
FWq B = .94180E-2
1.006409 s
899.39
B Flow
F A
51.92
fa
ix[ ','
WB.
4.223
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
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
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
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
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
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
Release
TASK: Perform Licensed Operator Actions to Establish a Liquid Waste
ALTERNATE PATH: None
FACILITY JPM NUMBER: NEW
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'.
- Place IMP-61 in MAN at 40%.
- 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
- 3 OP-141,
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
- 7 OP-118,
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
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
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
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)
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
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.
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
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.
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:
(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
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
JPM SRO-A.3
Radiological Controls
CANDIDATE:
EXAMINER:
Page I of 8
JPM SRO-A.3
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
TASK: Radiological Controls
ALTERNATE PATH: NA - Questions
NA - Questions
FACILITY JPM NUMBER:
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
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
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.
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"
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
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
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
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
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
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
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
imminent or has
occurred (See Note
4 on PAR
Flowchart).
NOTE: If using
Attachment B
conditions, this
should be YES due
to Containment
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
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
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
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
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
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
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.
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
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
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
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.
- Start EDG B.
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.
2*, occurred and check for proper breaker 126 has
response of EDG B output failed to open
breaker 126 * Notifies Unit SCO
Critical to
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
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
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:
- 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
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
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
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
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.
(RNO) STOP RCPs due to
isolating CCW
cooling flow to
TASK COMPLETE::_
STOP TIME:
Page 5 of 6
JPM COM-B. Ie
HARRIS
REGION II
INITIAL LICENSE EXAMINATION
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
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.
- 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
- 1SI-52, Alt High recirc
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
- 1SI-107, Alt High
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:
- ISI-3, Boron hlj
Tank Outlet
- ISI-4, Boron Inj
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
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
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>
- Secure RCP A
- 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)
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
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
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
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
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
N44 DIFFERENCE
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
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
TASK: Local Actions for a Dropped Rod Recovery
ALTERNATE PATH: None
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/
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
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
TASK: Manually Control Charging Due to a Loss of IA
ALTERNATE PATH: None
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
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
TASK: Start Up a Hydrogen Recombiner
ALTERNATE PATH: None
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/
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
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
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.
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