ML20151T592

Refers to 980817 Meeting Conducted in Region II Office at Licensee Request to Present self-assessment of McGuire Nuclear Station Performance.List of Attendees & Copy of Licensee Presentation Handouts Encl

ML20151T592
Person / Time
Site:	Mcguire, McGuire
Issue date:	08/26/1998
From:	Ogle C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Barron H DUKE POWER CO.
References
NUDOCS 9809100075
Download: ML20151T592 (54)

Text

__-_____-___

3 August 26, 1998 Duke Energy Corporation ATTN: Mr. H. B. Barron Vice President McGuire Nuclear Station 12700 Hagers Ferry Road Huntersv111e. NC 28078-8985

SUBJECT:

MEETING

SUMMARY

- MCGUIRE NUCLEAR STATION

Dear Mr. Barron:

This' refers to the meeting that was conducted at your request in the Region II office.on August 17. 1998, for you to present a self-assessment of McGuire Nuclear Station performance. A list of attendees and a copy of your presentation handout are enclosed.

It is our opinion that this meeting was beneficial in that it provided the NRC staff with a better understanding of McGuire Nuclear Station performance and your ongoing initiatives.

In accordance with Section 2.790(a) of the NRC's " Rules of Practice "

Part 2. Title 10. Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.

Should you have any questions concerning this meeting, please contact us.

Sincerely.

Original signed by:

Charles R. Ogle. Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos. 50-369. 50-370 /

License Nos. NPF-9. NPF-17 /

Enclosures:

1. List of Attendees

[

2. Licensee Presentation Handouts cc w/encls:

Michael T. Cash Regulatory Compliance Duke Energy Corporation 12700 Hagers Ferry Road Huntersville NC 28078-8985 cc w/encls cont'd: (See page 2)

[ TNy M,~

L P PDR

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DEC 2 cc w/encls cont'd: Distribution w/encls:

L. A. Keller F. Rinaldi. NRR Licensing - EC050 E. Lea. RII Duke Energy Corporation C. Ogle RII P. O. Box 1006 C. Pa ne. RII Charlotte. NC 28201-1006 PUBLI NRC Resident Inspector Legal Department (PB05E)

Duke Energy Cor) oration 422 South Churc1 Street Charlotte NC 28242-0001 Mr. Robert P. Gruber Executive Director Public Staff - NCUC P. O. Box 29520 Raleigh NC 27626-0520 J. Michael McGarry. III. Esq.

Winston and Strawn 1400 L Street NW Washington D. C. 20005 Mel Fry. Acting Director Division of Radiation Protection artment of Environmental N.Health C. Dep& Natural Resources

'3825 Barrett Drive Raleigh. NC 27609-7721 County Manager of Mecklenburg County 720 East Fourth Street Charlotte NC 28202 Steven P. Shaver Senior. Sales Engineer Westinghouse Electric Corporation 5929 Carnegie Boulevard. Suite 500 Charlotte NC 28209 Dr. John M. Barry Director Mecklenburg County epartment of Environmental rotection 700 North Tryon Street Charlotte NC 28203 Karen E. Long Assistant Attorney General N. C. Department of Justice P. O. Box 629 Raleigh. NC 27602 l OFFIE RII:DRP SImAftmE A j, l

l NME ELEA DATE S/ g f /98 8/ /98 .:. /98 8/ /98 8/ /98 8/ /98 8/ /98 l (NYT YES NO YES ND YES ND YES NO YES NO YES N0 YES 40 0FFICIAL RECORD CEPY DO(15ENT MME: C:VICGIT817.5L58 l

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}

1 1

LIST OF ATTENDEES NUCLEAR REGULATORY COMMISSION L. Reyes. Regional Administrator. Region II (RII)

J. Johnson. Deputy Regional Administrator. RII B. Mallett. Director. Division of Reactor Safety (DRS). RII C. Casto. Deputy Director. Division of Reactor Projects (DRP). RII H. Berkow. Director. Project Directorate II-2. Office of Nuclear Reactor Regulation (NRR)

C. Ogle. Chief, Branch 1. DRP. RII K. Landis. Chief. Engineering Branch. DRS. RII F. Rinaldi. Project Manager. NRR S. Shaeffer. Senior Resident Inspector McGuire Nuclear Station. RII W. Rogers. Senior. Reactor Analyst. DRS RII R. Moore. Reactor Inspector. DRS RII ,

l DUKE ENERGY CORPORATION - MCGUIRE NUCLEAR STATION (MNS)

H. Barron. Vice President. McGuire Nuclear Station (MNS)

M. Geddie. Station Manager. MNS B. Dolan. Safety Assurance Manager. MNS B. Travis. Mechanical Systems Engineering Manager. MNS ,

A. Bhatnager. Operations Superintendent. MNS I D. Jamil. Maintenance Superintendent. MNS O

e t

Enclosure 1 1

Pre-SALP Meeting j Systematic Assessment of Licensee Performance McGuire Nuclear Station August 17,1998 Enclosure 2

+. _ _ -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1 Agenda Performance Overview Brew surron Operations Ashok Bhatnagar Maintenance Dhiaa famil Engineering Bruce Travis Plant Support Mac ceaaie 4

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- Work Scope for Forced Outage OPS Superintendent Recommends Restart to PORC Successfully Used:

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- Personnel Safety Assessment Prior to Re-energizing Systems

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- Procedure Upgra-de

- Culture Shift  ;

i, Number and Significance have Downward Trend

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. Operator Training 1997 Hot License Class Results XRC Region II/ Duke Meeting to Clarify .

Expectations on Utility Developed-Exams-I Self AssessmentIdentified Key Areas for Improvement

- Implementation of Time Critical Actions

- Increased Simulator Time for HLP Students .

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_ . . . . - - - . . . . - - - . - . - - ~ . _ , , ,

Major Work Items Performed During Past 3 Outages Ice Condenser t

- unloaded and replenished 1,247 baskets Diesel Generators '!

- major overhaul of all 4 diesel engines Main Turbine

- HP turbine inspection and blade ring replacement  ;

., - one LP turbine inspection (Unit 1) 1

- 14 turbine valve replacements

- turning gear rebuild (Unit 1)

Electrical Generator

- generator and exciter inspection l

- generator stator rewedge

- generator retorque (Unit 2) -i!

"^ ^

- hydrogen cooler rebuild

]

i

i Major Work Items Performed During Past 3 Outages Rx Vessel Head =

- :aart length motor tube ins;aection (Unit 1)

Motors -

- 23 large motor replacement / refurbishment ,

' i Pumps

- 33 large pump inspection / rebuild / replacement Steam Gene ~rator

- replaced all 8 steam generators i

Operator Aid Computer -

=

- replaced both Units' OACs r

- - - . - - - - - . - ~ . . ~ .

i Major Work Items Performed During Past 3 Outages

' T.

i Feedwater Isolation Valves Actuator Realacement _

(Unit 1) t Continued work on high number of valves despite J shorter outages (approximately 500 per unit) i i

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Self-assessments-Procecure process improvement 4 Materiel condition upgrades

-_ - - - - - - ------..--a---. - - - - - - - - - - - - - - - - - - - - - - _ _ - - _ - - - . - - - - - - - - - - - _ _ . - - - - - - - - - _ _ - - _ _ _ _ - - - - - _ - _ - - _ _ _ - _ - - _ _ _ - _ _ _ - - - , - - - - , . - , _ _ _ _ _

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l Major Modifications / Upgrades Completed in 1997-8

• b.

Replaced all Steam Generators on ~ aoth units Replaced Operator Aid Computer oniaoth units Replaced eighta anc. final reactor coolant ,

pump motoi on iaoth units and installed a partial discharge monitoring system to detect motor degradation prior to failure i

Major Modifications / Upgrades Completed in 1997-8

• Replaced all 4 feedwater isolation valve actuators and mocified valve internals on Unit 1 .

• Completely rebuilt all 4 emergency diesel generator engines (8-11-98 XRC status meeting)

= Upgraded the refueling water storage tan s levelinstrumentation on both units 1

Major Modifications / Cpgrades Completed in 1997-8

• Replaced all 4 vital ~aattery banks anc. chargers j i

= Rep:. aced Unit 1 emergency *feedwater* isolation valves (89-10 u:pgrac.e)

• Modifiec. the XXA/KXB non-vita:. busses to i unitize the :.oads and reduce : potentia for dual unit trip

• Modifiec Unit 1 tur aine hyc.rau:ic oi:. system to ~]revent / limit tur aine shutc own jsis%l 1]

i

. t Major Modifications / Upgrades Scheduled for Future

• Replace Unit 2 feedwater isolation valve

. actuators and modified valve internals _ ..

Replace Unit 2. emergency feec. water isolation valves (89-10 upgrac.e) .

• Replace centrifugal c:aarging pump injection isolation valves (89-10 upgrade)

• Replace Unit 1 & 2 emergency feec. water recirculation va:.ves -

s n ,stp

6 Major Modifications / Upgrades Scheduled for Future i 7.

• Install new diesel aowered instrument air compressor system (ingrogress) i

. Conceptual de~ sign =forTarge emergency feedwater storage tank (working with CXS to j define scope)

• Comp:.ete remainder of KXA / KXB (non-vital busses) to unitize load

Major Engineering Assessments in 1997-8

~

• Emergency Diesel Generators

- MNS, MPR Associates,Nectra_Eng..(DE&S) i:

Emergency Feedwater ';

- MNS EFW Improvement Team l

- Duke General Office SITA Turbine Generator Reliability

- MNS, MPR Associates ,

i k

i Major Engineering Assessments in 1997-8  ;

.i t t Condensate Booster Pump, Motor Reliability

- MNS Motor Team, StructuralIntegrity Associates j Equipment Reliability Improvement

- MNS, FPI Inc.

i Root Cause Process Improvements i

• Identified significant root cause analysis '

weakness in 1995'

• Partnerec. wita CXS, OXS and FPI to develop 'l and refine Failure Investigation Process (MP)

• Trained all plant engineers on root cause failure mechanism in 1996 i

Root Cause Process Improvements l

, m.

• Advanced training for root cause mentors (approx. 8 in plant engineering)

Perform ap; proximately 80-100 formal root cause eva:.uations / year .

Root Cause. Program (XSD 212) backbone of equi:pment reliability improvement program -

Prevention; Detection; Correction A

9l J

Major Equipment Reliability Improvement Processes y s6

• Top EquipmentProiem Relia aility ,

(TEPR) Program _ _

• Corrective Action Review Board (CARB)

• Engineering Support Program Review Board (ESP)

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Fire Protection = .

Security

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• Radiation Protection Chemistry il

_ . _ _ _ _ _ ... _ . . 7 l

Fire Protection

, = .

Penetration Seals t

- Intrusive Inspections

- Configuration Database Fire Protection Flow Testing Operating Experience

• Responsibility Consolidation O

I Security

• Badee o Termination Process 1 .;

- Corrective Actions

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- Security Mod

- Single PAP t Tactical Readiness

- Consultation  :

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Radiation Protection

• Exposure

- Trend

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- Future Challenges Solid Radwaste

- Continuous Improvement Initiatives

- Outage Results

1 i

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Operational Quality and Safety of Operations

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