ML20197G255

Forwards Summary of 971121 Oversight Panel Meeting.List of Attendees & Handouts Encl

ML20197G255
Person / Time
Site:	LaSalle
Issue date:	12/19/1997
From:	Grant G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Subalusky W COMMONWEALTH EDISON CO.
References
NUDOCS 9712300398
Download: ML20197G255 (30)

Text

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December 19,L19971 Mr. W. T. Subalusky, Jr 1 184to Vlos President

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LaSalle County Station Commonwealth Edison Compar$

g i 2001 North 21st Road

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Marseilles,IL 81341 -

SUBJECT:

. - NRC OVERSIGHT PANEL MEETING

Dear Mr,

aa.aiay; The NRC Oversight Panel met with Commonwealth Edison and LaSalle County Station 1

- management on November 21,19g7. This management meeting was open to public ~

- observation. Enclosure 1 contains the associated meeting summary. Enclosure 2 3

contains the handout provided to the NRC Oversight Panel by Commonwesith Edison -

~

during the meeting.

1 i in accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10,-

LCode of Federal Regulations, a copy of this letter and its enclosures will be placed in the

' NRC's Public Document Room.

Sincerely,

! s/ G. E. - Grant

/

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Geoffrey E, Grant, Director Division of Reactor Projects Docket Nos.: 50 373;50-374?

License Nos.: NPF-11; NPF ?

Enclosures:

1.

Meeting Summary 2.

Meeting Handout See Attached Distribution f

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December 19, 1997?

9 Mr. W. T.' Subalusky, Jr.

~ Site Vice President LaSalle County Station Commonwealth Edison Company 2601 North 21st Road Marsellies,IL 61341 SUSJECT:

NRC OVERSIGHT PANEL MEETING

Dear Mr. Subalusky:

The NRC Oversight Panel met with Commonwealth Edison and LaSalle County Station

. management on November 21,1997. This management meeting was open to public..

observation. Enclosure 1 contains the associated meeting summary.- Enclosure 2 contains the handout provided to the NRC Oversight Panel by Commonwealth Edison during the meeting.

In accordance with Section 2,790 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's Public Document Room.

Sincerely, C<?

E.

s -

Geo y E.

ran 4 recto, Divi on of Reactor Projects Docket Nos.: Su-373; 50-374

' License Nos.: NPF 11; NPF-18

Enclosures:

1.-

Meeting Summary 2.

Meeting Handout See Attached Distnbution i

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W. Subalusky cc w/encis:

O. Kingsley, Nuclear Generation Group President and Chief Nuclear Officer M. Wallace, Senior Vice President, Corporate Services E. Kraft, Vice President BWR Operations Liaison Officer, NOC-BOD D. A. Sager, Vice President, Generation Support D. Farrar, Nuclear Regulatory Services Manager I. Johnson, Licensing Operations Manager Document Control Desk-Ucensing F. Dacimo, Plant General Manager P. Bames, Regulatory Assurance Supervisor Richard Hubbard Nathan Schloss, Economist Office of the Attomey General State Liaison Officer Chairman, Illinois Commerce Commission Distribution:

Docket File w/encls DRP w/encls FUBLIC IE-01 w/encls TSS w/encls A. Beach w/encls DRS (2) w/encls Deputy RA w/encls Rill PRR w/encls i

Rill Enf. Coord. w/encls RAC1 (E-Mail)

SRI LaSalle w/encls CAA1 (E Mail)

Project Mgr., NRR w/encls DOCDESK (E-Mail) l 1

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W. Subalusky '.

cc w/oncis:

O. Kingsley, Nuclear Generation Group President and Chief Nuclear Officer M. Wallace, Senior Vice

- President, Corporate Services E. Kraft, Vice President -

BWR Operations Unison Officer, NOC BOD D. A. Sager, Vice President, Generation Support D. Farrar, Nuclear Regulatory Services Manager

1. Johnson, Uconsing Operations Manager Document Contro! Desk-Ucensing F. Dacimo, Plant General Manager P. Bames, Regulatory Assurance -

. Supervisor Richard Hubbard

' Nathan Schloss, Economist Office of the Attomey General State Uaison Officer Chairman, Illinols Commerce Commission 4

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V Public Meeting Summary NRC Oversight Panel for LaSalle County Station I'

j November 21 Mananoment Meetinn Summary:

The licensee presented information contained in the applicable handout in Enclosure 2. During the licensee's presentation, the licensee provided clarification in response to NRC questions and comments. The licensee provided a status of the restart plan, discussed seveml material 4i condition improvements being implemented during the extended shutdown, presented their current assessment of operator performance, and discussed the status of license amendments needed before plant restart.

During the discJasion, the licensee indicated the following with regards to the effectiveness of

< improvement actions and current plant performance:

- Mr. Oliver Kingsley, Chief Nuclear Officer for Commonwealth Edison, stressed that he was "giving his personal word" that the licensee would not come to the NRC staff and ask permission to restart LaSalle County Station until they are assured the plant can restart safely. He wanted to avoid restarting the plant and then having a major event or significant design problem occur. He indicated they would continue to stress doing worft right the first time.

. Unit i startup had been targeted as April 2,1997. This date was a challenge, but achievable. Additional engineering and testing activities could raise additional issues, which could further delay startup.

The Restart Plan strategy for safe plant operations was about 70 percent complete. The licensee continued to see progress, especially with respect to out-of-service program implementation, plant labeling, shift tumover, and plant equipment challenges.

A significant change in human performance at LaSalle Station was apparent. The licensee was meeting its goals in this area, although they recognized that further

ii improvement was needed. The licensee indicated that there had been no ouMf-selvice errors in the last 3M months. However, this statement did not reflect " lesser' events.

The licensee was striving to have employees report even insignificant problems and two recent " time-outs" had been conducted in response to problems, such as cat-of-service problems. They had been working on driving down the threshold for ident'iying human 4

performance problems and they stated that unlan members were now writ.ing problem 4

identification forms involving other union members, a change from the past.

4

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The Restart Plan strategy for improving piant material condition was shout 80 percent complete. The licensee predicted the punch list (items remaining) would be small enough to close this strategy by the end of January 1998.

1

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Considerable progress had been seen in engineering effectiveness. The licensee was still taking actions to address engineering personnel qualifications and the ability to effectively resolve equipment problems in a timely manner.

The Restart Plan strategy for corrective action /self assessment improvement was closed and ready for NRC inspection in response to a question from the NRC staff, the licensee 4

ladicated that the Corrective Action Review Board was established as a standard long-term process for Commonwealth Edison plants as opposed to a short-tenn action.

The Operator High Intensity Training Program was complete and the closure package for the Restart Plan strategy involving training was being prepared.

With regard to the Restart Plan strategy for process improvements, the licensee had seen success in processirig of procedure changes and the ability of operators to control equipment.

The licensee currently had 67 open Corrective Action Records for Safety Assessment and Quality Verification organization findings which they believed was too high and was a i

continuing challenge.

The licensee had completed approximately 13,000 of an anticipated 22,000 outage activities. They were currently in the process of completing some of the more difficult activities, such as modifications.

During the discuss,len, the NRC staff communicated the following considerations:

The NRC staff questioned the system engineering tumover rate and experience level.

The licensee responded that although they had experienced some tumover of system engineers, a large part was replacement of contractors with Commonwealth Edison employees. Raising the standards for engineers had, in some cases, highlighted performance problems, but new people were changing the work philosophy. The licensee also maintained that the experience level of system engineers had increased in the last 6 to 8 months. In addition, the licensee indicated that the engineering assurance group had resulted in an increase in the quality of engineering work products such that they could now go back to a sampling approach.

The NRC staff questioned the methodology the licensee was using to track completion of Restart Plan items. The licensee described the work management system being used to track the completion of physical work. In response to an NRC staff question regarding independent reviews of Restart Plan implementation, the licensee responded that an assersment in this area was planned for January 1998.

During a discussion on material condition improvements, the NRC staff related a recent NRC finding involving numerous minor material condition problems in containment and the fact that licensee management had not been in containment in over 8 months. The Site Vice-President indicated that he had been in containment after this issue was raised and that he had found similar conditions. The licensee maintained that plant management was now getting into hard to access areas and every area in the plant had been assigned a resporlible manager.

2

The NRC staff recognized the considerable scope of hardware impromnents the licensee was attempting to implement and commended the extensive licensee efforts -

aimed at human performance improvement. However, the NRC staff noted that the licensee was still at an easy stage of the performance improvement process. The NRC staff urged the licensee te focus on what's really needed for restart and what titelr oversight efforts are finding, including the measures they are using to judge progress.

The NRC s'aff expressed optimism that if the licensee took the right steps, LaSalle County Sta'.,on was in a position to quickly become a good performer.

Attendees:

NE A. Beach, Regional Administrator, Region Ill G. Grant, Director, Division of Reactor Projects (DRP)

R. Capra, Director, Project Directorate 1112, Office of Nuclear Reactor Regulation M. Leach, Chief, Operator Licensing Branch T. Vogel, Acting Cl,lef, DRP Branch 2 M. Huber, Senior Resident inspector, LaSalle D. Hills. Project Engineer E. Duncan, Reactor Engineer Commonwealth Edison O. Kingsley, Chief Nuclear Officer, Comed W. Subalusky, Site Vice-President, LaSalle F. Decimo, Plant General Manager, LaSalle S. Smith, Plant Manager, LaSalle T. O' Leary, Executive Staff, Comed I. Johnson, Licensing Director, Comed B. Riffer, Quality and Safety Assessment Manager, LaSalle T. Broccolo, Corporate Assessment Manager, Comed J. Bailey, Restart Manager, LaSalle D. Farr, Operations Manager, LaSalle G. Poletto, Site Engineering Manager, LaSalle D. Boone, Site Services Manager, LaSalle D. Sanchez, Training Manager, LaSalle W. Jakielse, Shift Manager, LaSalle J. Fiesel, Mechanical Maintenance Department Supervisor, LaSalle D. Jenkins, General Attomey, Comed T. Poindexter, Attomey (Winston & Strawn), Comed D. Evans, Liason, Comed C. Beny, LaSalle P. Rosier, LaSalle Communications, Comed J. Schrage, WMD, LaSalle -

J. Walker, Corporate Assessment, Comed T. Cannon, Equipment Operator, LaSalle D. Sergenti, Radiation Protection Technician, LaSalle P. Soenksen, Instrument and Control Planner, LaSalle 3

i Commonwealth Edison Management Meeting Handout 1

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EEEIl Station Direction 1

World Class Performance i

i Safe, Long, Uneventful Run 1

Safe, Uneventful Startup November 21,1997 i

NRC Region III-Lisle, Illinois l

LaSalle

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President /CNO Opening Remarks Kingsley o

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e Restart Plan Status i

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Operator Training Farr e

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Restart Action Plan.

ygggy Strategy 2 - Action Plan 2.1 Human Performance e Goal - Achieve a Step Change improvement in Human Performance as Measured by:

> Event Free Clock

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> Open Significant Procedure Adherence PIFs LaSalle 8

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Table dspisys number of erms during the month. Graph dspiny total number of erras for the year.

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e High Intensity Training (HIT) for Operators e MARC Process /CFR/ Rewards & Recognition e FLS Assessment e Bargaining Unit / Department Head Meetings

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e Design Change Packages 294 77 i

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e Engineering Requests 1437 280 i

e Work Request Tasks 6395 2022 e Surveillance Tasks 1165 453 e Preventative Maint. Tasks 508 126 LaSaHe

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e Turbine Building Ventilation j

e Condensate / Condensate Booster Pumps e Main Condenser e Motor Driven Reactor Feed Pumps l

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e Main Steam Isolation Valves i

l e Meteorological Tower Relocation j

e Reactor Manual Control System LaSalle j

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Path presentlyis Reactor I,

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Egggl Material Condition - CD-10 Window i

e Reactor Water Cleanup System e ECCS Suction Strainers (NRCB 96-C3) i e Main Condenser I

e Feedwater System e Reactor Head Vent Valve i

j e Reactor Core Isolation Cooling & item l

e Reactor Building Closed Cooling Water System l

e Turbine Building Closed Cooling Water System e Electro-Hydraulic Control System i

l e Lake Blowdown System i

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l Eggg Materiel Condition - Remaining

. CR / AEER Ventilation (VCNE) 1 e Oscillating Power Range Monitors (GL 94-02) l l

e Secondary Containment e HELB 1

l e Drywell Sump indicators l

e KM Relays eIRMs/SRMs i

e Reactor Recirculation System i

l e FW Control System j

e Primary Containment Penetrations (GL 96-06) j l

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l EEEIl Dynamic Exam Results 1

e Recent (10/24/97) Results:

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>Two Crews (10 Individuals) Fascd Their Simulator a

Exam l

> One Crew " Passed with Remediation" i

- All three crews did not " Emergency Depressurize" in a l

timely manner when the temperature limits of the drywell were challenged.

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e A Formal Root Cause was Conducted j

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l Root Cause Team Findings:

e inappropriate Management Decision

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k individuals in HIT remediation will not be allowed to participate in the NRC annual requalification examination process until remediation has been l

successfully completed.

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i e Exam Scenario Quality

> Strengthen the Exam Validation Process

> Reviewed Currently Existing Exam Materials i

> Upgrade the Simulator Containment Model

> Acquire Additional Instructor Resources i

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ggggy License Amendments Requiredfor Unit 1 Restart f

i Planned r4RC i

Amendment Submittal Submitted Required Approved l

LAR 262: Delete reference to Reactor Steam Pressure 12/12/97 3/13,"38 from Condenser Low Vacuum Isolation per DCPs 9700461/2 LAR 255-01: HELB Leak Detection in Secondary 11/24/97 03/13/98 Containment

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LAR 178-02: VC/VE Filter Testino 09/26/97 01/23/98

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LAR 258: Post-LOCA Hydrogen instrument Channel 10/15/97 02/27/98 L

Calibration Gas

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LAR 214: Control Room Rad Monitorinstrumentation 07/01/97 10/09/97 LAR 254: Change Definition of Channel Calibration to 07/02/97 09/15/97 Exempt RTDs and Thermocouples LAR 252: Feedwater/ Main Turbine Reactor Vessel Water 04<04/97 07/29/97 Level Hioh Trip i

OTHER LICENSING ACTIONS Planned NRC Action Submittal Submitted Reovired Approved i

Submittal of position on venting ofleak chase channels 11/26/97 3/13/98 durino CILRT. NRC SER to be issued.

l Clarification of SBO SER reoardino battery capacity maroin 10/3/97 3/13/98 l

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