ML17191B382

From kanterella
Jump to navigation Jump to search
Discusses 990521 Meeting in Downers Grove,Il.Purpose of Visit to Meet Risk Mgt Staff Collectively Prior to Visiting Each Plant.Forwards Attendance List & Licensee Presentation
ML17191B382
Person / Time
Site: Dresden, Byron, Braidwood, Quad Cities, LaSalle  Constellation icon.png
Issue date: 06/17/1999
From: Grobe J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Kingsley O
COMMONWEALTH EDISON CO.
References
NUDOCS 9906240242
Download: ML17191B382 (27)


Text

'6 Mr. Oliver D. Kingsley President, Nuclear Generation Group Commonwealth Edison Company ATTN: Regulatory.Services Executive Towers West Ill 1400 Opus Place, Suite 500

.June. 17., 1999

SUBJECT:

SENIOR REACTOR ANALYST SITE VISIT

Dear Mr. Kingsley:

This refers to a meeting conducted by Region Ill Senior Reactor Analysts (SRA) at the Commonwealth Edison Company (ComEd) office in Downers Grove, Illinois, on May 21, 1999.

The purpose of the visit was to meet with your risk man~gement staff collectively, prior to visiting each of the ComEd plants, to discuss your initiatives in the risk area, and to establish a dialog between the SRAs and your risk management staff. Also discussed were your specific risk insights and risk tools used at the Quad Cities Station, which is a plant that is participating in the NRC pilot inspection program. Material presented during this meeting is enclosed.

As you are aware, the Nuclear Regulatory Commission is transitioning to a risk-informed framework for its inspection and oversight prograrT1 for commercial nuclear power plants. The new program will focus our inspections on activities and systems where potential risks are greater using site-specific PRA insights. The meeting between your staff and our risk analysts provided a basis for better agreement on the importance of issues on which we will routinely interact during the risk-informed inspection and oversight program. We will be visiting each of the ComEd plants to gain additional insights into the plant-specific use of risk insights in the day-to-day operation and shutdown activities. The SRAs will contact your staff to decide a convenient time to conduct these plant-specific discussions.

  • In accordance with Section 2. 790 of the NRC's "Rules of P*ractice," a copy of this letter and its enclosures will be placed in the NRC's Public Document Room.

990p240242 990617 PPDR ADOCK 05000237 PDR

0. Kingsley

-2;.

If you have any questions regarding this meeti.ng please contact me at (630) 829-9700.

Sincerely, Original Isl S. A. Reynolds John A.. Grobe, Director Division of Reactor Safety Docket Nos. :.S0-456; 50-457; 50-454; 50-455;

' 50-237; 50-249; 50-373; 50-374; 50-254; 50-265 License Nos. NPF-72; NPF-77; NPF-37; NPF-66; DPR-19; DPR-25; NPF-11; NPF-18; DPR-29; DPR-30

Enclosures:

    • 1.
2.

Attendance List Licensee Presentation See Attached Distribution DOCUMENT NAME: G:DRS\\COM06'l}9.wpd To receive* co of this document, Indicate In the box: "C" =Co without attachmenVendosure "E" = C OFFICE Riii E Riii NAME SBurgess:sd '2:ib JG robe DATE 06/ 4-/99.

OFFICIAL RECORD COPY with attachmenVendosure "N" = No co r..

0. Kingsley cc w/encls:

D. Helwig, Senior Vice President H. Stanley,.PWR Vice President C. Crane, BWR Vice President Distribution:

SAR (E-Mail)

RPC (E-Mail)

R. Krich, Vice President, Regulatory Services DCD - Licensing T. Tulon, Braidwood Site Vice Presiden~

K. Graesser, Byron Site Vice President M. Heffley, Dresden Site Vice President J. Benjamin, LaSalle Site Vice President J. Dimmette, Jr~. Quad Cities Site Vice President K. Schwartz, Braidwood Station Manager. -

W. Levis, Byron Station Manager P. Swafford, Dresden Station Manager T. O'Connor, LaSalle Station Manager W. Pearce, Quad Cities Station Manager T. Simpkin, Braidwood Regulatory Assurance Supervisor B. Adams, Byron Regulatory Assurance Manager F. Spangenberg, Dresden Regulatory Assurance Manager P. Barnes, LaSalle Regulatory Assurance Supervisor C. Pete~on, Quad Cities Regulatory Affairs Manager M. Aguilar, Assistant Attorney General State Liaison Officer State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission W. Leech, Manager of Nuclear MidAmerican Energy Company I

NRR Project Mgrs.

Braidwood, Byron,*

Dresden, LaSalle, Quad Cities w/encls J. Caldwell, Riii w/encls B. Clayton, Riii w/encls SRls Braidwood,.Byron, Dresden, LaSalle, Quad Cities w/encls.

DRPw/encls DRSw/encls

  • Riii PRR w/encls
  • PUBLIC IE-01 w/encls Docket File w/encls IEO (E-Mail)

DOCDESK (E-Mail)

GREENS

. ".... *, ~

I

,If * :

I

\\

(

....i \\.. : ---...L

0. Kingsley cc w/encls:

o~ Helwig, Senior Vice President R. Stanley, PWR Vice President C. Crane, BWR Vice President R. Krich, Vice President, Regulator}' Services DCD ~ Licensing T. Tulon, Braidwood Site Vice President K. Graesser, Byron Site Vice President M. Heffley, Dresden Site Vice President J. Benjamin, LaSalle Site Vice President _

J. Dimmette, Jr.; Quad Cities Site Vice President K. Schwartz, Braidwood Station Manager _

W. Levis, Byron Station Manager P. Swafford, Dresden Station Manager T. O'Connor, LaSalle Station Manager W. Pearce, Quad Cities Station Manager T. Simpkin, Braidwood Regulatory Assurance Supervisor B. Adams, Byron Regulatory Assurance Manager F. Spangenberg, Dresden Regulatory Assurance Manager*

P. Barnes, LaSalle Regulatory Assurance Supervisor C. Peterson, Quad Cities Regulatory Affairs Manager M. Aguilar, Assistant Attorney General State Liaison Officer State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission W. Leech, Manager of Nuclear MidAmerican Energy Company

Attendance List - ComEd/NRC Risk* Meeting, May 21, 1999 Com Ed B. Bohlke, Vice President, Engineering B. Burchill, Chief Engineer, Risk Management S. Dort, ComEd Licensing Director T. Fuhs, Regulatory Assurance,' Quad Cities Y. In, Risk Management Engineer, Braidwood/Byron (Downers Grove)

E. Jebsen, Risk Management Engineer, Quad Cities _*

R. Johnson, Risk Management Engineer, Dresden M. Kalache, Risk Management Engineer, LaSalle (Downers Grove)

B. Lamb, Engineering, Quad Cities R. Linthicum, Risk Management Engineer, Braidwood M. Melnicoff, Risk Management Engineer, Braidwood/Byron (Downers Grove)

X. Polanski, Risk Management Engineer, Quad Cities C. Settles, Division Chief, Resident Inspectors (Illinois Department of Nuclear Safety)

J. Steinmetz, Risk Management Engineer (Downers Grove)

S. Burgess, Senior Reactor Analyst, Rill M. Parker; Senior Reactor Analyst, Rill

COMMONWEALTH EDISON

. RISK MANAGEMENT BRIEFING

. FOR NRC REGION III SENIOR REACTOR ANALYSTS CotnEd Office Downers Grove, IL.

Frid~y, May 21, 1999 -

/

.* COMED RISK MANAGEMENT

.

  • HISTORY
    • 1981 Zion Probabilistic Safety Study.
  • 1988 Individual Plant Examinations
  • 1993 On-line Risk Management. *

.. *. *. 1994 Modified IP Es

  • 1996 IPE External Events

~

  • 1997 Maintenance* Rule e
  • I
  • 1998 Risk Mgmt. Upgrade Initiative.
  • 1999.0n-line Risk Monitors

Braidwood/Byron PRA History

. Submitted Braidwood IPE Report

. Received RAI for Braidwood

. Submitted Byron IPE Report

. Received RAI for Byron

. Submitted RAI response for both_ Stations, including modified IPE

.., Received SER for Braidwood*

. * * *Received SER for Byron

  • ... _ Util~~ing Enhanced* IPEs*to support
  • on-line risk _fnanagement _an4 MRule

. Upgraded PRA for both Stations

. Braidwood Certification Peer Review

. Byron Certification Peer Review

' Version reported to NRC in sensitivity study in IPE submittals.

June 30, 1994 January 26, 1996 April 28, 1994 February 1, 1996 March 27, 1997 October 27, 1997.

December 3, 1997 June :1, 1999. __

July,* 1999 January, 2000

Dresden PRA History

. Submitted IPE Report

. Received Initial.RAl *

. Submitted Final RAI response,

    • including modified-IPE

. Received SER

. Utilizing Enhanced* IPEs to support on.,. line risk man(_lgement and MRule

. Upgraded PRA

.

  • Certification Peer Review
  • Version of modified IPE submitted to NRC in I 0/26/94 RAI Response..

January 28, 1993 August 24, 1994 June 28, 1996 *

. October 2, 1997

  • March 15, 1999.

January, 1998. -

I

LaSalle PRA History

. NUREG/CR;..4832 Vol. 3, Sandia, RMIEP August, 1992

. Submitted IPE Report *

. April 28, 1994

.

  • No*RAI Received

. Received SER

. Utilizing IPE to support on-line

  • risk management and MRule

...Upgraded _PRA *

  • . Certification Peer Review.

March 14, 1996

. June 15,.1999 November, 1999

.e

Quad Cities PRA History

  • Submitted IPE Report December 13, 1993
  • Received Initial RAI June 9-, 1994 Submitted Final RAI response, e

_August 30, 1996 -

including modified IPE _

  • Received SER July 9; 1997 -
  • Utilizing Enhanced* IPE to support

-_ on~line risk management and MRule

. -Upgraded PRA _

April 5, 1999 e

_Certification Peer Review _*_

October, 1999

~

  • Version of modified IPE submitted to NRC in 8/8/94 RAJ Response.

Braidwood Station IPEEE Status

. Submitted IPEEE Report *

. Received RAI

. Submitted Plant Specific Responses *-to RAI June 27, 1997 July9, 1998 January 29, 1999

. Responses to generic IPEEE questions will be submitted 30 days after NRC approves. the final EPRI tailored collaboratio_n group project responses to these questions. -

(NEI target is June, 1999)

. 9

_. Outside expert will complete an independent review of the ~raidwood

Byron Station IPEEE Status

. Submitted IPEEE Report

.. Received RAI

. Submitted Pl.ant Specific Responses to RAI December 23, 1996 July 23,.1998.

January 29, 1999

.. Responses.to generic IPEEE questions will be submitted 30 days after NRC approyes the final EPRI tailored collaboration

  • group project r~sponses to*these que'stions (NEI target is June, 1999) ~ -- *

. 9

. Outside expert will_ complete an independent re:view of the.Byron*

-IPEEE in June, 1999

Dresden SJation IPEEE Status

. Submitted IPEEE Report December 30, 1997

. Received RAI December 14, t998

. ComEd is upgrading Dresden fire risk evaluation Incorporate lessons. learned from upgrading

  • Quad Cities fire risk evaluation.
  • Complete Unit 2 upgrade.

September 30, 1999

.. Will submit revised IPEEE submittal to NRC Upgraded Dres<l:en fire risk evaluation Includes RAI.responses

  • LaSalle Station IPEEE Status

. NUREG/CR-4832.Vol. 9, Sandia, RMIEP March, 1993

. Submitted IPEEE Report -

April 28, 1994

/

. No RAI Received

. Outside expert will complete an independent review of the LaSalle

_ IPEEE* in June, 1999 -

e

Quad Cities Station IPEEE Status

. Submitted IPEEE Report F ebrµary 1 7, 1997

-. Received RAI

_-November 26, 1997*

. Def erred RAI Response pending ISP January27, 1998

-. -ComEd upgraded fire risk ev<;lluation --_

May, 1998 - pres-ent

-Extensive cable mapping/FMEA

-Upgraded Fire PRA based on Upgraded PRA Success paths use all available equipment Modeled realistic response using EOPs, _-

9-

. Revised IPEEE submittal to NRC

  • Includes RAI Responses MC;ly 31, 1999 -

Shutdown Risk Management History

..

  • Decision to use ORAM as shutdown risk management tool

.* 1993

  • Shutdown Risk Management Peer Group formed.

1996

    • ORAM models completed_ for all stations 1998
  • Shut.down Safety Management Program procedure approved., 1998

~-*_Merge On-line and shutdown risk_.monitors

--*-~

1999

RISK MANAGEMENT.

IMPROVEMENT INITIATIVE

  • .Review (independent) all PRAs
  • Upgrade/Optimize PRATools
  • .Assess Current Risk Mgmt Practices
  • Establish PRA Consistency Guidelines *
  • Balance Resources Among 71h Projects

~

  • Deploy New On-line Risk Monitors..
  • Upgrade Current Risk Mgmt Practices

.

  • Establish New Risk Mgmt Practices

UPGRADE/OPTIMIZE

. PRA TOOLS

  • .
  • Upgrade Plant Models

.* * -*Initiating Events

. * - Systems/Components.

- Human Performance.

-. *Update Reliability/Failure* Data-

  • Optimize for On~line Use. *

- Linked Fault Tree Structure*

  • . -* Modularized Architecture

CURRENT RISK MANAGEMENT PRACTICES*

  • On-line Maintenance Planning
  • Maintenance. Rule Performance* Criteria
  • . Screening Engineering Requests *

.

  • Evaluating* Design Changes

.**

  • System/Component Risk Ranking
  • Severe Accident Management
  • Shutdown Maintenance Planning e*
    • HISTORY OF COMED ON-LINE RISK MONITORS
  • 19~3
  • Zion OSPRE (Operational Safety PREdictor) deployed

> *Objective to monitor/tren*d on-line risk* (ISEG)

> Table lookup of precalculated PRA results

> Screen design groups systems by* function

> CDF & CDF Ratio (RAW) displayed.

>

  • Risk color. bands* based on "DID rules" /judgement
  • 1 994 Quad Cities OSPRE deployed

>* Objective to. support on-line maintenance

  • e

> Table lookup of precalculated PRA results e

> Screen design improved from Zion OSPRE

> CDF, RAW, & LERF *displayed

>

  • Risk bands based on draft PSA Applications Guide

>... Protective responses" defined for each risk band

. HISTORY OF COMED ON-LINE RISK MONITORS

  • 4/18/95 "On-Line Maintenance Poli*cy" issued*

> Sets ComEd on~line maintenance objective

> *Requires pre-determined risk envelope

  • > Requires con.sistehcy* with.EPRI PSA Applications Guid*e
  • Sprin*g '95 generic risk co.lor bands ~et.for_ all plants

>. Based on "zero maintenance model"

> Re_lated to draft. PSA Applications Guide:-

CDP =. E-6/CDP = E-5/CDF *= E-3/yr

-assuming gen~ric 7-day work window e.

> Adopted most restrictive set of thresholds:

G reen/3/Yellow /20/0range/3 5 /Red

  • > lmpleme.nted by station-specific procedures

~

HISTORY OF COMED ON-LINE RISK MONITORS

  • Late 19*95 Dresden OSPRE deployed

> Essentially the same design as Quad *OSPRE

  • > Preceeded by "risk templates" (pre-calculated PRA results tables) to ev_al~ate 1 2-week work cycle
  • _ > RM Engr. supported WC use of both temprates and OSPR-E
  • Late, 1995 Braidwood* & Byron initiated 12~week
  • work cycle risk evaluatio.ns to support on-line ma int

> Initiated rolling _development of risk,templates *

e.

> Work cycle r.isk evaluations prepared py RM Engr.

e

> *On-line risk monitors def_er_red pending PRA conversions to linked fault tree (LFT)

HISTORY OF COMED ON-LINE RISK MONITORS

-

  • 1996 LaSalle EOOS On-line Risk Monitor Deployed

> Conve-rted RMIEP LFT Model to EPRI CAFTA

> Implemented -in EPRI EOOS risk monitor

, > -Applied generic risk color response bands

> Pilot for ComEd on-line risk monitors

-* 1 9 pre_s-ent: On-line maintenance risk evalu~ted -

> Blend bf "PRA Risk" and DID rules/cautions*

> OSPRE at Dresden, Quap & Zion (before shutd.own)

> Risk templates* at Bra.idwood & Byron,

e

  • > -All PRA risk apply generic risk bands
  • HISTORY OF COMED ON-LINE RISK MONITORS
  • NGG "On-Line Maintenance" Procedure Deployed

> Sets administrative controls for on-line maintenance o_n SSCs important to safety

>- Specifies process/schedule for 1 2-week work cycle evaluation

  • 9

> Requires Operat_ing Shift to "continuously evalu~te the risk of -the scheduled on-line maintenance activity based upon conditions... -*~*

>, Reinforces complian*ce with individual LC Os/ A TRs

  • FURTHER IMPROVEMENT PLANNED IN 1 999.
  • > Deploy new OSPRE/EOOS on-line risk monitors

> Customize Se.ntinel defense-in-depth logic models* _

for each ComEd station *

> Upgrade on-line_ risk monitors to Sentinel user interface with OSPRE/EOOS in background

DEPLOY ON-LINE RISK MONITORS

  • Involve Ops/Work Control in Design
      • Train All U*sets in Tool/Results *
  • Apply in Engineers Continuing Training *
  • Evaluate Impact on Risk Profiles.*
  • *
  • Strengthen Risk Tre,nding

. ~ Implement Living PRA

ESTABLISH NEW RISK

.. MANAGEMENT PRACTICES

  • Technical Specifications

-*

  • -* Surveillance Intervals.
  • Inservice Inspections
  • Maintenance Prioritization *
  • Procurement Classification*
  • Inservice Testing