ML021680568

Plant Performance Update Meeting, McGuire Nuclear Station

ML021680568
Person / Time
Site:	Mcguire, McGuire
Issue date:	06/06/2002
From:	Barron H Duke Energy Corp
To:	Office of Nuclear Reactor Regulation
Shared Package
ML021680561	List: ML021680564 ML021680568
References
Download: ML021680568 (20)

Text

Plant Performance Update Meeting June 6, 2002

';011 11'1 151!i! 1jj 1II1l1]III.I IIl11,11 i

~II. ' III ' III l j linli%!17W1!III iii, il 1:tI I il

!\I1ll'I!

1IIII Enclosure 2

Agenda

• Introduction- Brew Barron

• Operational Performance- Dhiaa Jamil

- Generation Status Trending

- 2EOC14 Refueling Outage

- ALARA Performance

- Correct Component Verification

• Miscellaneous- Bryan Dolan

- Corrective Action Program

- Special Nuclear Material

- Security 2

Operational Performance 3

McGuire Nuclear Station GENERATION STATUS TRENDING 2001 - 2003 Actual vs. Target o

0 LL.

C-)

100%

90%

80% -

- rv==Unit 2 (2.8 days)

Main Steam Unit 2 (0.44 days)

Add Oil to 2B NCP Cu Pressure Trip

tf M

70% -

Q C.

CD 60%

0M L- 1EOC14 (38.2 days) 50% Cond. Boost Pmp Mtrs.

0 Busline Relay Mod 2EOC15 (30 days)

Non-vital Spare Inverter 40% (KXS to KXA) 1EOC15 (25 days) Rx Vessel 10-year ISI C-) Vital Inverters Replace.

Main Gen. Volt Reg. Main Gen. Volt Reg No S/G Work No S/G Work Cu Rx Vessel 10-year ISI Unit. (3133 days) 30% - CA Tank Tie-in SG Main FW Reg Valv -

10W% Vessel Head Bare Metal Inspection E) failed capacitor

~0 20% - 2EOC14 (32.3 days)

TARGET REACTOR C.F. ('M CA Tank Tlein.

wi - l 10% - Cond. Boost Prmp MI. 2C ID -WELYACTUAL I 1D% Vessel Head

-a Bare Metal Inspection 0% I.

_- II111 ] I rI1 1 II T T ITI 111-111 ........ 111 IT ....7.... 1..11...1........

I II II I FTT I-

.0 a Q (0 0 a C) 0. >. a (U M 0)0a M 0) . w

>, 3 I so>

ClM 0w

> 0 0

1UI :f  ; -7 -7 O? 2 IL I5 M 7 <: Q N r-N 7u 0.<

il' tD OOW4

- 0 N N ' (L I- a)r7 N1 .q M ) to N tanu N4 r N 2001 II II -20022 i -2003 1 Generation Status Trending 4

2EOC14 Refueling Outage 5

Completed Auxiliary Feedwater Storage Tank Tie In 6

Repaired CRDM K-8 Intermediate Canopy Seal Weld Intermediate Canopy Seal Approx. 6 ft.

Reactor Head 7

Performed 100% Bare Metal Head Inspection -

No Corrosion or Boron Found 8

r-. .

9

Shutdown/Startup Performance Improvements

• Tuning of process control system

• Tuning of valve actuators

• Sequencing of steam dump valves

• Procedural improvements

• Simulator and training improvements

• Manual reactor / turbine trip from low power 10

ALARA Performance

• Changes

- Step change in ALARA planning and scheduling

- Radiation Work Permit setpoint adjusted down to more effectively use dosimetry as ALARA tool

- Focused on radiation worker desired behavior prior to and during the outage

- PIP threshold changes 11

ALARA Performance (continued)

• Results

- Desired worker behavior demonstrated

- Desired increase of PIPs at lower threshold was obtained

- Comprehensive self-assessment of outage radiation practices - complete 12

2EOC1 4 Refueling Outage

• Zero LERs

• Zero events

• Zero injuries

• 32 dcjys 13

Correct Component Verification (CCV)

• Defined specific behaviors associated with CCV

• Created a CCV flag

• Conducted classroom and flow loop scenario training

• Targeted observations with CCV focus

• 2EOC14 was co mpleted without a CCV event

• Similar focus on CCV is now underway in operations and chemistry 14

Miscellaneous 15

Corrective Action Program PIP Significance Categories ACA No Cause Analysis 16

Corrective Action Program

• PIP Action Codes

- Corrective Actions to Prevent Recurrence (CAPR)

• Directed at the Root Cause of Category I and 2 PIPS

- Corrective Actions (CA)

• Directed at CAQ

- Elective / Enhancement Actions (ELEC)

- Structure helps focus corrective action effectiveness reviews on highest priority actions (CAPRs) 17

Special Nuclear Materials

• Completed comprehensive inventory

• No discrepancies 18

Security m

• No concerns about schedule for compliance with NRC order.

19

Questions 20