ML030730662
| ML030730662 | |
| Person / Time | |
|---|---|
| Site: | Callaway |
| Issue date: | 08/23/2002 |
| From: | Gody A Operations Branch IV |
| To: | Randolph G Union Electric Co |
| References | |
| 50-483/02-301 50-483/02-301 | |
| Download: ML030730662 (8) | |
Text
Callaway Rev. 0, Feb. 27, 2002 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility:
Callaway Date of Examination:
August 2002 Exam Level:
RO Operating Test No.:
B.1 Control Room Systems System / JPM Title Type Safety Code
- Function
- a. Recover a Dropped Control Rod D, S 001A4.06 (2.9 /3.2) 51
- b. Manually Operate MSIVs Which Fail to Actuate M, A, C, L 2
013A4.01 (4.5/4.8)
C1
- c. Depressurize and Block Safety Injection D, S, L 3
010A4.01 (3.7 /3.5)
S4
- d. Perform 'B' RHR Pump Non-Surveillance Run N, S 4 (Pri) 005A4.01 (3.6/3.4)
S2
- e. Main Turbine Mechanical O/S Trip Test 045A2.17 (2.7 /2.9)
S3
- f. Respond to a Failed Power Range Instrument D, 5, L 7
015A2.02 (3.1/3.5)
S5
- g. Restoration of CCW From Inadvertent CIS B N, S, L 8
008A4.01 (3.3/3.1)
S6 B/U Start 'A' CTMT Cooler Fan D, S, A 5
022A4.01 (3.6 / 3.6)
Backup B.2 Facility Walk-Through
- a. Emergency Boration Per FR-S.1 D, A, R, P 004A2.14 (3.8/3.9)
P1
- b. Locally Close Valves for CIS A D, R, P 5
103A2.03 (3.5/3.8)
P2
D, A, P 6
064A4.01 (4.0 / 4.3)
P3
- 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, (P)lant FACILITY REPRESENTATIVE:W CHIEF EXAMINER:
V i DATE:g4g2/
DATE: 7&6-NUREG-1021 Revision 8
Callaway Rev. 0, Feb. 27, 2002 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility:
Callaway Date of Examination:
August 2002 Exam Level:
SRO (I)
Operating Test No.:
B.1 Control Room Systems System / JPM Title Type Safety Code
- Function
- a. Recover a Dropped Control Rod D, S 001A4.06 (2.9/3.2)
S1
- b. Manually Operate MSIVs Which Fail to Actuate M, A, C, L 2
013A4.01 (4.5/4.8)
C1
- c. Depressurize and Block Safety Injection D, S, L 3
010A4.01 (3.7/3.5) 34
- d. Perform 'B' RHR Pump Non-Surveillance Run N, S 4 (Pri) 005A4.01 (3.6 / 3.4)
S2
- e. Main Turbine Mechanical O/S Trip Test D, S, A 4 (Sec) 045A2.17 (2.7 /2.9)
S3
- f. Respond to a Failed Power Range Instrument D, S, L 7
015A2.02 (3.1/3.5)
S5
- g. Restoration of CCW From Inadvertent CIS B N, S, L 8
S 008A4.01 (3.3/3.1)
S6 B/U Start 'A' CTMT Cooler Fan D) Sy A 5
022A4.01 (3.6 / 3.6)
Backup B.2 Facility Walk-Through
- a. Emergency Boration Per FR-S.1 D, A, R, P 004A2.14 (3.8/3.9)
P1
- b. Locally Close Valves for CIS A D, R, P 5
103A2.03 (3.5/3.8)
P2
D, A, P 6
064A4.01 (4.0/4.3)
P3
- 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, (P)lant FACILITY REPRESENTATIVE:.P CHIEF EXAMINER:
NUREG-1021 DATE:
DATE:
/
Revision 8
Callaway Rev. 0, Feb. 27, 2002 ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility:
Callaway Date of Examination:
August 2002 Exam Level:
SRO (U)
Operating Test No.:
B.1 Control Room Systems System / JPM Title Type Safety Code
- Function
- a. Manually Operate MSIVs Which Fail to Actuate M, A, C, L 2
013A4.01 (4.5/4.8)
C1
- b. Perform 'B' RHR Pump Non-Surveillance Run N, S 4 (Pri) 005A4.01 (3.6 /3.4)
S2
- c. Restoration of CCW From Inadvertent CIS B N, S, L 8
008A4.01 (3.3 /3.1)
S6
- d.
- e.
- f.
- g.
B/U Start 'A' CTMT Cooler Fan D, S, A 022A4.01 (3.6 / 3.6)
Backup B.2 Facility Walk-Through
- a. Emergency Boration Per FR-S.1 D, A, R, P 004A2.14 (3.8 / 3.9)
P1
D, A, P 6
064A4.01 (4.0/4.3)
P3 C.
- 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, (P)lant FACILITY REPRESENTATIVE:
CHIEF EXAMINER:
/
DATE:___
DATE:
7 ~62_
7 NUREG-1021 Revision 8
Callaway Rev. 1, Jun. 24, 2002 ES-301 Administrative Topics Outline Form ES-301 -1 Facility:
Callaway Date of Examination:
August 2002 Examination Level:
RO Operating Test Number:
Administrative Describe method of evaluation:
Topic/Subject
- 2. TWO Administrative Questions A.1 Conduct Of Determine If Rod Insertion Limit Has Been Exceeded Operations /
G 2.1.7 (3.7)
Al RO/SRO Evaluate Plant Performance Conduct Of Determine Dilution Requirements Operations /
G 2.1.25 (2.8)
A2 RO/SRO Interpret Reference Material A.2 Equipment Control /
Calculate RHR Pump Run Time For Flood Up Refueling Process G 2.2.27 (2.6)
A3 RO A.3 Radiation Control/
Calculate Stay Time Stay Times G 2.3.10 (2.9)
A4 RO A.4 Emergency Determine Status Of Control Room Annunciators Procedures / Plan G 2.4.48 (3.5)
A5 RO Knowledge Of RERP FACILITY REPRESENTATIVE:
CHIEF EXAMINER:
DATE:
_______2.
DATE:
Revision 8 NUREG-1021 A
Callaway Rev. 0, Feb. 27, 2002 ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Callaway Date of Examination:
August 2002 Examination Level:
SRO Operating Test Number:
Administrative Describe method of evaluation:
Topic/Subject
- 2. TWO Administrative Questions A.1 Conduct Of Determine If Rod Insertion Limit Has Been Exceeded Operations /
G 2.1.7 (4.4)
Al RO/SRO Evaluate Plant Performance Conduct Of Determine Dilution Requirements Operations /
G 2.1.25 (3.1)
A2 RO/SRO Interpret Reference Material A.2 Equipment Control /
Determine Actions For Valve Stroke Test Surveillance G 2.2.12 (3.4)
A3 SRO Procedures A.3 Radiation Control Reportability For Exceeding Exposure Limits Exposure Limits G 2.3.4 (3.1)
A4 SRO A.4 Emergency Emergency Event Classification Procedures / Plan G 2.4.41 (4.1)
A5 SRO RERP Notifications FACILITY REPRESENTATIVE:
Lu4
CHIEF EXAMINER:
NUREG-1021 DATE:
-7/_-___
DATE:
Revision 8
Callaway Rev. 0, Feb. 27, 2002 Appendix D Scenario Outline Form ES-D-1 Callaway Plant Initial License Exam - August 2002 SCENARIO # ILE2002DS1 EXAMINERS:
APPLICANTS:
INITIAL CONDITIONS:
100% Reactor Power, 'B' RHR Pump OOS TURNOVER: See Turnover Sheet Event Event Event Description KA Number No.
Type
- A N
Increase Letdown Flow From 75 GPM to 120 GPM 004A4.06 t = 0 (RO, SRO)
(3.6 /3.1)
B I
'B' S/G Level Channel 529 Fails High 016K3.12 t = 10 (BOP, SRO)
(3.4/ 3.6)
C I
VCT Level Channel 149 Fails High 004A2.18 t =20 (RO, SRO)
(3.1 /3.1)
D C
'B' Circulating Water Pump Trip 075A2.02 t = 25 (ALL)
(2.5 /2.7)
E R
Turbine Setback to 75 % Power 045K4.12 t = 25 (RO)
(3.3 /3.6)
F M
Hotwell Instrumentation Leak - Loss of Feed 054AA2.01 t = 35 (ALL)
(4.3 /4.4)
G C
Turbine Automatic Trip Failure 007EA1.07 PRE (BOP, SRO)
(4.3 / 4.3)
H M
Large Break LOCA 011EK3.12 PRE (ALL)
(4.4 / 4.6)
I C
ESF Bus NB01 Lockout (IPE / PRA) 062A2.04 PRE (ALL)
I (3.1 /3.4)
- (N) Normal (R) Reactivity (I) Instrument (C) Component (M) Major FACILITY REPRESENTATIVE:
LDATE:
CHIEF EXAMINER:
NUREG -1021 DATE:
Revision 8, Supplement 1
-4 (0/b ý-
Callaway Rev. 0, Feb. 27, 2002 Appendix D Scenario Outline Form ES-D-1 Callaway Plant Initial License Exam - August 2002 SCENARIO # ILE2002DS2 EXAMINERS:
APPLICANTS:
INITIAL CONDITIONS: 30% Reactor Power, 'B' RHR Pump OOS TURNOVER: See Turnover Sheet Event Event Event Description KA Number No.
Type
- A N
Swap Charging From NCP To CCP 004A4.08 t=0 (RO, SRO)
(3.8 / 3.4)
B I
Pressurizer Pressure Channel 455 Fails High 027AA2.15 t = 10 (RO, SRO)
(3.7 /4.0)
C I
Steam Flow Channel 542 Fails High On 'D' S/G 059A2.11 t = 20 (BOP, SRO)
(3.0/3.3)
D C
Steam Generator Tube Leak On 'D' S/G 037AK3.05 t = 25 (ALL)
(3.7 /4.0)
E R
Plant Shutdown Due To S/G Tube Leak 004A4.01 t = 25 (RO)
(3.8 / 3.9)
F M
Steam Generator Tube Rupture On 'D' S/G (IPE / PRA) 038EA2.02 t = 40 (ALL)
(4.5 / 4.8)
G C
Failure Of 'D' FWIV To Automatically Close 013A4.01 PRE (ALL)
(4.5 /4.8)
H M
S/G Safety Stuck Open On 'D' S/G 035A2.01 t = 42 (ALL)
(4.5/4.6)
F/
- (N) Normal (R) Reactivity (I) Instrument (C) Component (M) Major
,CILITY REPRESENTATIVE:
. L'p,.)A.J
&( /
DATI CHIEF EXAMINER:
I DATi
/
V
(
E:
7 /1*o".
E 7Ii'4o5L1 Revision 8, Supplement 1 I fli, ;ýk-NUREG -1021
Callaway Rev. 0, Feb. 27, 2002 Appendix D Scenario Outline Form ES-D-1 Callaway Plant Initial License Exam - August 2002 SCENARIO # ILE2002DS B/U EXAMINERS:
APPLICANTS:
INITIAL CONDITIONS:
80% Reactor Power, 'B' RHR Pump OOS TURNOVER:
See Turnover Sheet Event Event Event Description KA Number No.
Type
- A I
Pressurizer Level Channel 459 Fails Low 011A2.11 t = 0 (RO, SRO)
(3.4 / 3.6)
B C
Letdown Isolation Valve Fails Closed 004A2.07 t = 0 (RO, SRO)
(3.4/ 3.7)
C N
Place Excess Letdown In Service 028AA1.05 N/A (RO, SRO)
(2.8 / 2.9)
D C
'A' RCP High Vibration 015AA1.23 t = 20 (ALL)
(3.1 / 3.2)
E R
Plant Shutdown Due To RCP High Vibration 004A4.01 t = 20 (RO)
(3.8 / 3.9)
F I
'A' S/G PORV Failure 041A4.06 t = 35 (BOP, SRO)
(2.9/3.1)
G M
Loss of Off-Site Power and NB02 056AA2.44 t = 40 (ALL)
(4.3/4.5)
H C
Auto Reactor Trip Failure 029EA1.12 PRE (ALL)
(4.1 / 4.0)
I C
TDAFP Fails To Auto Start 061A2.04 PRE (ALL)
(3.4/3.8)
J C
Loss of All AC due to NE01 Failure (IPE / PRA) 055EA2.02 PRE (ALL)
(4.4/4.6)
- (N) Normal (R) Reactivity (I) Instrument (C) Component (M) Major FACILITY REPRESENTATIVE:
]U/-
DATE:
CHIEF EXAMINER:
__DATE:
NUREG -1021 Revision
-*1I 4 8, Supplement 1