ML090420391

San Onofre - 2009-02 - Final Exam Outline

ML090420391
Person / Time
Site:	San Onofre
Issue date:	02/05/2009
From:	McKernon T O Operations Branch IV
To:	Southern California Edison Co
References
50-361/09-301, 50-362/09-301, ES-301, ES-301-1 50-361/09-301, 50-362/09-301
Download: ML090420391 (7)

Text

ES-301 Administrative T opics Outline Form ES-301-1 Facility:

SONGS 2 & 3 Date of Examination:

02/02/2009 Examination Level SRO Operating Test Number:

NRC Administrative Topic (see Note) Type Code* Describe Activity to be Performed Conduct of Operations D, R 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation (4.4).

JPM: Calculate a makeup to the RWST. (J215A)

Conduct of Operations D, P, R 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (4.7).

JPM: Perform manual calculation of RCS flow rate. (J165A)

Equipment Control N, R 2.2.13 Knowledge of tagging and clearance procedures (4.3).

JPM: Review clearance boundaries. (New).

Radiation Control M, R 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (3.6)

JPM: Determine stay time for work to be performed. (J216A). Emergency Plan N, R 2.4.41 Knowledge of emergency action level thresholds and classifications. (4.6)

JPM: Classify an emergency event. (New). NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required. NUREG-1021, Revision 9.1 Page 1 of 3 2009A NRC ES-301-1 rev 0.doc ES-301 Administrative T opics Outline Form ES-301-1 NUREG-1021, Revision 9.1 Page 2 of 3 2009A NRC ES-301-1 rev 0.doc *Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; for 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1) (P)revious 2 exams ( 1; randomly selected)

Administrative Topics Outline Task Summary NUREG-1021, Revision 9.1 Page 3 of 3 2009A NRC ES-301-1 rev 0.doc A.1.a The candidate is directed to perform a blended makeup to the RWSTs at a total flow of 40 gpm. The Plant Monitoring System is not available. The candidate will determine the required Boric Acid Flow Rate and the Primary Makeup Water flow rate for the required RWST makeup. The critical tasks include determining Primary Water and Boric Acid flow ra tes and completing Prerequisites for SO23-3-2.2 Attachment 14. This is a modified bank JPM.

A.1.b The candidate will be required to ca lculate RCS flow rate with the Plant Monitoring System (PMS) unavailable. The critical task will be to determine if the calculated flow rate is in compliance with Technical Specifications. This JPM was

modified due to procedural changes and new RCP Pump curves.

A.2 The Boric Acid Makeup Pump 2MP174 is to be cleared for mechanical work on the pump casing. The shift manager dire cts the candidate to review the clearance boundaries selected and report findi ngs when complete. The critical task is to identify two errors in the clearance boundary. This is a new JPM.

A.3 The candidate will determine stay time for work to be performed and take action for a change in radiological conditions. The critical task is to select the correct REP for work to be performed and determine st ay time for the operator. This is a modified bank JPM.

A.4 The candidate will perform an EPIP event classification based on lack of control room alarms, damage to ESF equipment and current plant conditions. The critical task is to determine the proper classification. This is a new JPM.

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 NUREG-1021, Revision 9.1 Page 1 of 4 2009A NRC ES-301-2 rev 0.doc Facility: SONGS Units 2 and 3 Date of Examination:

02/02/2009 Exam Level:

RO SRO(I)

SRO (U) Operating Test No.:

NRC Control Room Systems

@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function S-1 001 - Control Rod Drive System (J045FS)

Dampen ASI oscillation A, D, S 1 S-2 013 - ESFAS (J042FS) Verify proper EFAS actuation A, D, L, S 2 S-3 EPE 009 - SBLOCA (J228FS) Perform Subcooled Pressure Control actions A, D, E, L, S 3 S-4 EPE - Steam Generator Tube Rupture (J094FS) Verify correct SG isolated following SGTR A, D, E, L, S 4 - S S-5 026 - Containment Spray System (J145FS) Restore Containment Spray A, D, E, L, S 5 S-6 064 - Emergency Diesel Generators (J188S) Reenergize Bus 2A06 from Unit 3 Diesel Generator M, P, S 6 S-7 012 - Reactor Protection System (J047S) Channel A Narrow Range Pressure Transmitter failure D, P, S 7 In-Plant Systems

@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P-1 039 - Main and Reheat Steam System (J022F) Manually open the Atmospheric Dump Valve A, D 4-S P-2 APE 068 - Control Room Evacuation. (J122) Rad waste operator actions for SD from outside CR E, M, R 1 P-3 EPE 055 - Station Blackout (J202) SBO actions to cross connect to Unit 3 D, E 6 ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 NUREG-1021, Revision 9.1 Page 2 of 4 2009A NRC ES-301-2 rev 0.doc

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (EN)gineered safety feature - / - / 1 (control room system) (L)ow Power / Shutdown 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected) (R)CA 1 / 1 / 1 (S)imulator

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 NUREG-1021, Revision 9.1 Page 3 of 4 2009A NRC ES-301-2 rev 0.doc NRC JPM Examination Summary Description S-1 The candidate will use the Control Rod Drive System to dampen an Axial Shape Index oscillation. The alte rnate path requires a Reactor Trip when two CEAs fall into the core. This is a bank JPM under t he Control Rod Drive System - Reactivity Control safety function.

S-2 The candidate will validate proper EFAS actuation per SO23-3-3.22 ESFAS System Operation, attach ment #13. Validation check determines that AFW P-141 requires a manual start as well as A-394 AFW pump room fan. This is a bank JPM under the Engineered Safety Features Actuation System - Reactor Coolant System Inventory Contro l safety function.

S-3 The candidate will perform Sub-Cooled Pressure Control actions per SO23-12-9, Functional Recovery, RCS Pressure Contro l using the HPSI System. The alternate path requires aligning HPSI valves and/or pumps to facilitate core cooling. This is a bank JPM under the Emergency Core C ooling System - Reactor Pressure Control safety function.

S-4 The candidate will verify the correct SG is isolated following a Steam Generator Tube Rupture. The alternate path requires that the candidate recognize that the wrong SG was isolated and realigns for the ruptured SG. This JPM requires the operator to use an alternate means of SG pressure control due to a Main Steam Isolation Signal. This is a bank JPM under the Steam Bypass System - Secondary

System Heat Removal from Reactor Core safety function.

S-5 The candidate will restore Containment Spray per SO23-12-11, EOI Supporting Attachments, Floating Step 12, Monitor Containment Pressure. The alternate path requires the candidate to perform RNO acti ons for spray flow when it is determined that it cannot be initiated by normal means. This is a bank JPM under Containment Spray System - Containment Integrity safety function.

S-6 The candidate will reenergize Bus 2A06 from the Unit 3 Emergency Diesel Generator per SO23-12-11, EOI Supporting Attachm ents, Attachment 24, Supplying 1E 4 KV Bus from Opposite Unit Diesel. Two critical steps added to load the diesel generator with the salt water cooling pum p and the component cooling water pump. This is a modified JPM in the AC Electrical Dis tribution System - Electrical safety function.

S-7 The candidate will take corrective actions for Channel "A" Narrow Range Pressurizer Pressure Transmitter failure per SO23-13-18 and SO23-3-2.12. This is a bank JPM under the Reactor Protection System - Instrumentation safety function.

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 NUREG-1021, Revision 9.1 Page 4 of 4 2009A NRC ES-301-2 rev 0.doc NRC JPM Examination Summary Description (cont)

P-1 The candidate will be required to manually open the Atmospheric Dump Valve per SO23-3-2.18.1. This is a bank JPM under the Heat Removal from Reactor Core safety function. The alternate path requires the candidate to open the ADV manually.

P-2 The candidate will perform Shutdown From Outside the Control Room action for the Rad Waste Operator per SO23-13-2, Shutdown fr om Outside the Control Room. Four critical steps added to ensure Component Cooling Water is aligned to

the Reactor Coolant Pumps. This is a modified JPM with a Reactivity Control safety function.

P-3 The candidate will perform Station Blackout actions to energize 1E 480V bus 2B04 per SO23-12-11 from Unit 3 using MCC BQ for the cros s connect. This is and AC Electrical Distribution electrical safety function. This is a bank JPM with a PRA significant action.