ML030730662

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Initial Exam - 08/2002 - Final Operating Outlines
ML030730662
Person / Time
Site: Callaway Ameren icon.png
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)
v • d • e


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
c. Locally Start NE01 Emergency DG (IPE / PRA) 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 DATE:g4g2/

CHIEF EXAMINER: DATE: 7&6-Vi 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 008A4.01 S (3.3/3.1) S6 B/U Start 'A' CTMT Cooler Fan D) SyA 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
c. Locally Start NE01 Emergency DG (IPE / PRA) 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 DATE: ____ ,___

CHIEF EXAMINER: DATE: /

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 (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
b. Locally Start NE01 Emergency DG (IPE / PRA) 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: DATE:___

CHIEF EXAMINER: 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 1. ONE Administrative JPM, OR Description 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: DATE: _______2.

A CHIEF EXAMINER: DATE:

NUREG-1021 Revision 8

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 1. ONE Administrative JPM, OR Description 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 DATE: -7/_-___

CHIEF EXAMINER: DATE:

NUREG-1021 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: -4 (0/b ý-

CHIEF EXAMINER: DATE:

NUREG -1021 Revision 8, Supplement 1

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)

  • (N) Normal (R) Reactivity (I) Instrument (C) Component (M) Major F/,CILITY REPRESENTATIVE: . L'p,.)A .J &( / DATIE: 7 /1*o".

---. ----I E 7Ii'4o5L1-CHIEF EXAMINER: I fli,;ýk-

/

DATi V (

NUREG -1021 Revision 8, Supplement 1

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: -*1I 4 _

CHIEF EXAMINER: __DATE:

NUREG -1021 Revision 8, Supplement 1

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