ML20210N268

Discusses Paritially Withheld Chairman Briefing by Ceco on 951116

ML20210N268
Person / Time
Site:	Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle
Issue date:	11/13/1995
From:	Tschiltz M NRC
To:	Shirley Ann Jackson, The Chairman NRC COMMISSION (OCM)
Shared Package
ML20210N181	List: ML20210N177 ML20210N268 ML20210N295 ML20210N338 ML20210N376 ML20210N427
References
FOIA-97-178 NUDOCS 9708250166
Download: ML20210N268 (3)

Text

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November 13, 1995 Note To: Chairman Jackson r

From: Michael Tschiltz'V l

Subject:

CHAIRMAN BRIEFING BY COMMONWEALTH EDISON, i THURSDAY, NOVEMBER 16, 1995 Coordinated With: Annette Discussion: Performance at Dresden, Quad Cities, Zion, Braidwood and LaSalle are of concern to the staff. Dresden, Quad Cities and Zion all continue to be challenged by material condition and human performance problems. Significant work remains to fully resolve equipment, chnical support and work control issues. .,

_Ja In the last several years Comed has taken significant steps to improve performance including hiring management from outside the company;< reorganization; i.gcreased engineering capability; improvement of craft skills; pertormance benchmarking with other utilities.

REX _E.NT__ DEVELOPMENTS AT COMED SITES Dresden - On November 10, 1995, Comed announced that all further work efforts on the Dresden_ Unit _2_ refueling _ outage were on_ hold-pending completion of outage replanning. Dresden Unit 2 has been in a refueling outage (D2R14) since June 2, 1995. The outage was 3 originally scheduled to last 100 days; however, emerging work items and a slow work control process have continued to delay outage completion. The in-progress work will be completed or restored to a safe condition. All work p~ackages will_be_" walked

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down" by the licensee. The remaining work E~Ehe tace will be

~ escheduled and the manloading will be read'usted.

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'N Byron - A midcycle inspection of steam generator tubes at Byron Unit i revealed a significant number of circumferential indications. With the inspection near completion _2696 _

circumferential_ indications have been identified at the top of the tube sheet. SG tubes with circumferential cracking will be sleeved since further plugging of tubes would require derating the Unit. The preliminary schedule for this work has Byron Uni _t i remaining shutdown _for the remainder of the yea _r.

t 9708250166 970820 PDR FOIA PARADIS97-178 PDR

Q SG TUDE REPAIR CRITERIS -

On November 9, 1995, the staff approved the license amendment request for SG tube plugging criteria for outside diameter stress corrosion cracking (ODSCC) at Braidwood Unit 1 and Byron Unit 1 (see YELLOW TAB)

SITE

SUMMARY

Braidwood o Material condition at the site has degraded significantly as evidEhesd by the large number of unattended 4@R57Cpumps and valves throughout the plant.

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o Recent Unit 1 SG inspections found extensive steam generator tube degradation to be progressing more rapidly than previously predicted, o Craft skill ranting _ revealed. inabilities to perform fundimental operations such as repacking ~ valves, assembling gasketed flanges and safely installing groundir.g devices.

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O Continues to be an above average performer with strengths in )

teamwork and interdepartmental communications and #

conservative programmatic approaches. ,

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Unit 1 is currently in a mid-cycle outage for steam generator inspections. .w c4 s ca p4w e Dresden o Significant effort to reinvicorate performance : #

initiatives. Mr. Heffl_ey_ is the station manager,7gprovement o Improved management response to events'and in the critical questioning of performance and actions initiated to prevent recurrence.

o Wor}Lbacklog. ia_ con s idered_high. No gignificant progres reducing the backlog. Operator work aroundi~hMVe 15een',s in reduced but are still considered substantial.

O Poor material condition and numerous examples of poor performance by maintenance personnel.

o Radiation protection _ skills _and performance level is low,

e Lidella o Poor material condition is the largest problem. Causes include-poor'dfibign, weak ~eT15Uieelihg~l~ high tolerance for work arounds and maintenance work processes.

O Procedures are considered. inefficient _.and_ confusing. The change procias~is viewed as ineffective.

O Equipment problems continue to present operational problems.

l Thsre~1c a-largn umhbiiF or work arounds and operators are slow to recognize work arounds.

Quad CitiLi l

0 Management team viewed as strong. Management oversight and safety focus in the control room are viewed as strengths.

O Maintenance work control _ptqqesses, skill of the craft, and configuratiod~ control are consTdered problem areas.

O Material condition remains poor but is improving. Quality of work is a problem, o Operations procedural adherence and personnel errors in the conduct of routine operations continue to be a problem.

ZLon o Site _ performance .in. the_1ast_6_ mon _ths _ha.s been poor as

?videnced by a large number of personnel errors, violations, and deteriorating material condition. This is seen to be as a result of a long history of ineffective corrective actions, low standards for performance and management complacency.

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o Non-outage work backlog remains high (approx 1900 items). A reduction in backlog has not occurred. Maintenance personnel are unable to work more than the immediate needs of the plant which causes continued deterioration of the plant.

o Performance in collective radiation exposure is in the industry's fourth quartile.

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