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                            Docket Noi 50-373'
-
            '
!
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  '
Docket Noi 50-373'
                            Docket No. 50-374
'
                            Commonwealth Edison Company.
'
                          . ATTN:   Mr..Cordell Reed-
Docket No. 50-374
                    e               Senior Vice President
Commonwealth Edison Company.
          .'.             iPost Office Box 767
. ATTN:
                          . Chicago, IL 60690-
Mr..Cordell Reed-
                          . Gentlemen:                                                           ,.
e
                            This refers to'the special. maintenance team inspection conducted by Ms._S. Eick
Senior Vice President
                            and others of this office;on May.1-5, 15-19, and 25,.1989. This inspection
.'.
                            covered activities at L'aSalle County Station, Units 1 and 2 as authorized.by
iPost Office Box 767
    '
. Chicago, IL 60690-
                            NRC Operating Licenses NPF-11 and NPF-18, and the inspection ~ findings that were
. Gentlemen:
                            discussed with Mr. D. Galle and others of your staff.at the conclusion of the
,.
                            inspection.
This refers to'the special. maintenance team inspection conducted by Ms._S. Eick
                            The inspection.was conducted to assess and evaluate your support and
and others of this office;on May.1-5, 15-19, and 25,.1989.
                            implementation of maintenance to assure that plant structures, systems, and
This inspection
                            components reliably perform on-demand. Various activities'were evaluated to
'
                            determine if. maintenance was accomplished, effective, and adequately assessed
covered activities at L'aSalle County Station, Units 1 and 2 as authorized.by
                            by_your.own quality; verification process.
NRC Operating Licenses NPF-11 and NPF-18, and the inspection ~ findings that were
                            The enclosed copy of our. inspection report identifies specific areas examined
discussed with Mr. D. Galle and others of your staff.at the conclusion of the
                            during the~ inspection. .Within these areas, the. inspection consisted of a
inspection.
                                                        .
The inspection.was conducted to assess and evaluate your support and
                          ' selective examination of procedures and representative records, observations,
implementation of maintenance to assure that plant structures, systems, and
                            and interviews with personnel. In an attempt to. focus on those activities
components reliably perform on-demand.
                            which are most risk significant,. insights from LaSalle County Station's
Various activities'were evaluated to
                            Probabilistic Risk Assessment study, performed by the NRC, were used to select
determine if. maintenance was accomplished, effective, and adequately assessed
                            systems and components'important to safety.
by_your.own quality; verification process.
                            Plant performance since January 1989 was good in the areas of reactor trips,
The enclosed copy of our. inspection report identifies specific areas examined
                            safety system actuations, and forced outage rate. Overall, the inspection
during the~ inspection. .Within these areas, the. inspection consisted of a
                            team concluded that maintenance at LaSalle County Station appeared to be
.
                            satisfactorily performed and effective. The team identified strengths and
' selective examination of procedures and representative records, observations,
                            weaknesses in the maintenance process, which are highlighted in the executive
and interviews with personnel.
                            summary. Section 4.0~of the-inspection report provides a synopsis of your
In an attempt to. focus on those activities
                                                    .
which are most risk significant,. insights from LaSalle County Station's
                            maintenance program.
Probabilistic Risk Assessment study, performed by the NRC, were used to select
                            .The most significant weaknesses identified were: (1) instances of poor
systems and components'important to safety.
                            communication between corporate and site that resulted in inadequate corrective
Plant performance since January 1989 was good in the areas of reactor trips,
                            action on a 10 CFR 21 report regarding potential common mode failure of more
safety system actuations, and forced outage rate.
                            than.50 motor-operated valves; (2) instances of ineffective direction of
Overall, the inspection
                            maintenance activities that resulted, for example, in lack of QC involvement
team concluded that maintenance at LaSalle County Station appeared to be
                          iin surveillance testing, and inadequate controls to monitor the performance                               j
satisfactorily performed and effective.
                            of degraded solenoid operated discharge valves of the fuel oil transfer pumps
The team identified strengths and
                                                                                                                                      i
weaknesses in the maintenance process, which are highlighted in the executive
                                                                                                                              i l   l
summary.
                                6907050256 890628                                                                                 \
Section 4.0~of the-inspection report provides a synopsis of your
                                PDR ADOCK 05000373
.
                                                                                                                                h0
maintenance program.
                                                                                                                                      '
.The most significant weaknesses identified were:
                                Q                  PDC
(1) instances of poor
                                                                                                                              4
communication between corporate and site that resulted in inadequate corrective
action on a 10 CFR 21 report regarding potential common mode failure of more
than.50 motor-operated valves; (2) instances of ineffective direction of
maintenance activities that resulted, for example, in lack of QC involvement
iin surveillance testing, and inadequate controls to monitor the performance
j
of degraded solenoid operated discharge valves of the fuel oil transfer pumps
i
l
l
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6907050256 890628
\\
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PDC
h0
PDR
ADOCK 05000373
'
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                  Commonwealth Edison Company             2
s
                                                                                  JUN 2 81989
JUN 2 81989
                  for Unit 2 emergency diesel generators; (3) instances of inadequate engineering
Commonwealth Edison Company
                  support that resulted in poor Technical Staff review of procedures used to
2
                  verify operability of the five emergency diesel generators, and limited
for Unit 2 emergency diesel generators; (3) instances of inadequate engineering
                  involvement with cause/ failure analysis associated with Program Analysis Data
support that resulted in poor Technical Staff review of procedures used to
                  Sheets; and (4) in many instances there was an overall low level of system
verify operability of the five emergency diesel generators, and limited
                                .
involvement with cause/ failure analysis associated with Program Analysis Data
                  awareness and technical knowledge of System Engineers. Although some actions
Sheets; and (4) in many instances there was an overall low level of system
                  were in progress to address these concerns, increased management attention is
.
                  required to affect needed' improvement.
awareness and technical knowledge of System Engineers.
                  During this inspection, certain.of your activities appeared to be in violation
Although some actions
i                 of NRC requirements, as specified in the enclosed Notice.     A written response
were in progress to address these concerns, increased management attention is
                  is required.
required to affect needed' improvement.
During this inspection, certain.of your activities appeared to be in violation
i
of NRC requirements, as specified in the enclosed Notice.
A written response
'
'
                  In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of
is required.
                  this letter, the enclosures, and your response to this letter will be placed
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of
                  in the NRC Public Document Room.
this letter, the enclosures, and your response to this letter will be placed
                  The responses directed by this letter and the accompanying Notice are not
in the NRC Public Document Room.
                  subject to the clearance procedures of the Office of Management and not
The responses directed by this letter and the accompanying Notice are not
                  Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.
subject to the clearance procedures of the Office of Management and not
                  We will gladly discuss any questions you have concerning this inspection.
Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.
                                                            Sincerely,
We will gladly discuss any questions you have concerning this inspection.
                                                            " Original Signed by i:. W. C:or-- E"h
Sincerely,
                                                            Hubert J. Miller, Director               #
" Original Signed by i:. W. C:or-- E"h
                                                            Division of Reactor Safety
#
                  Enclosures:
Hubert J. Miller, Director
                  1.     Notice of Violation
Division of Reactor Safety
                  2.     Inspection Reports
Enclosures:
                            No. 50-373/89010(DRS);
1.
                            No. 50-374/89010(DRS)
Notice of Violation
                  cc w/ enclosures:
2.
                  T. Kovach, Nuclear
Inspection Reports
                      Licensing Manager
No. 50-373/89010(DRS);
                  G. J. Diederich, Station
No. 50-374/89010(DRS)
                      Manager
cc w/ enclosures:
                  DCD/DCB (RIDS)
T. Kovach, Nuclear
                  Licensing Fee Management Branch
Licensing Manager
                  Resident Inspector, RIII
G. J. Diederich, Station
                  Richard Hubbard
Manager
                  J. W. McCaffrey, Chief, Public
DCD/DCB (RIDS)
                      Utilities Division                                                             I
Licensing Fee Management Branch
                                                      ye               .
Resident Inspector, RIII
                  RIII                RI                            I           RII       Rill n
Richard Hubbard
                  $5 ws+9                          RIIL['
J. W. McCaffrey, Chief, Public
                                                  /f,%+ _
Utilities Division
                                                                                            /f/6"A
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                      Commonwealth Edison Cotepany   3   JUN 2 81989
! ,.-
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                      Distribution Cont'd
:< ;, _
                      David Rosenblatt, Governor's
Commonwealth Edison Cotepany
                    ,    Office of Consumer Services
3
                      Commissioner'Curtiss, OCM/JC
JUN 2 81989
                      K. Hart, NRR/LPEB
<
                      Director / Division of Reactor
i.i -
                          Safety RI, RII, RIV, RV
Distribution Cont'd
                                                        .
David Rosenblatt, Governor's
                                                                      i
Office of Consumer Services
,
Commissioner'Curtiss, OCM/JC
K. Hart, NRR/LPEB
Director / Division of Reactor
Safety RI, RII, RIV, RV
.
i
22._ . _-._
22._ . _-._
}}
}}

Latest revision as of 00:51, 2 December 2024

Forwards Maint Team Insp Repts 50-373/89-10 & 50-374/89-10 on 890501-05,15-19 & 25 & Notice of Violation.Insp Team Conclusion That Maint Satisfactorily Performed & Effective Noted.Weaknesses Discussed
ML20245K791
Person / Time
Site: LaSalle  
Issue date: 06/28/1989
From: Miller H
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Reed C
COMMONWEALTH EDISON CO.
Shared Package
ML20245K794 List:
References
NUDOCS 8907050256
Download: ML20245K791 (3)


See also: IR 05000373/1989010

Text

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JUN 2 81989

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Docket Noi 50-373'

'

'

Docket No. 50-374

Commonwealth Edison Company.

. ATTN:

Mr..Cordell Reed-

e

Senior Vice President

.'.

iPost Office Box 767

. Chicago, IL 60690-

. Gentlemen:

,.

This refers to'the special. maintenance team inspection conducted by Ms._S. Eick

and others of this office;on May.1-5, 15-19, and 25,.1989.

This inspection

'

covered activities at L'aSalle County Station, Units 1 and 2 as authorized.by

NRC Operating Licenses NPF-11 and NPF-18, and the inspection ~ findings that were

discussed with Mr. D. Galle and others of your staff.at the conclusion of the

inspection.

The inspection.was conducted to assess and evaluate your support and

implementation of maintenance to assure that plant structures, systems, and

components reliably perform on-demand.

Various activities'were evaluated to

determine if. maintenance was accomplished, effective, and adequately assessed

by_your.own quality; verification process.

The enclosed copy of our. inspection report identifies specific areas examined

during the~ inspection. .Within these areas, the. inspection consisted of a

.

' selective examination of procedures and representative records, observations,

and interviews with personnel.

In an attempt to. focus on those activities

which are most risk significant,. insights from LaSalle County Station's

Probabilistic Risk Assessment study, performed by the NRC, were used to select

systems and components'important to safety.

Plant performance since January 1989 was good in the areas of reactor trips,

safety system actuations, and forced outage rate.

Overall, the inspection

team concluded that maintenance at LaSalle County Station appeared to be

satisfactorily performed and effective.

The team identified strengths and

weaknesses in the maintenance process, which are highlighted in the executive

summary.

Section 4.0~of the-inspection report provides a synopsis of your

.

maintenance program.

.The most significant weaknesses identified were:

(1) instances of poor

communication between corporate and site that resulted in inadequate corrective

action on a 10 CFR 21 report regarding potential common mode failure of more

than.50 motor-operated valves; (2) instances of ineffective direction of

maintenance activities that resulted, for example, in lack of QC involvement

iin surveillance testing, and inadequate controls to monitor the performance

j

of degraded solenoid operated discharge valves of the fuel oil transfer pumps

i

l

l

i

6907050256 890628

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h0

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ADOCK 05000373

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JUN 2 81989

Commonwealth Edison Company

2

for Unit 2 emergency diesel generators; (3) instances of inadequate engineering

support that resulted in poor Technical Staff review of procedures used to

verify operability of the five emergency diesel generators, and limited

involvement with cause/ failure analysis associated with Program Analysis Data

Sheets; and (4) in many instances there was an overall low level of system

.

awareness and technical knowledge of System Engineers.

Although some actions

were in progress to address these concerns, increased management attention is

required to affect needed' improvement.

During this inspection, certain.of your activities appeared to be in violation

i

of NRC requirements, as specified in the enclosed Notice.

A written response

'

is required.

In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of

this letter, the enclosures, and your response to this letter will be placed

in the NRC Public Document Room.

The responses directed by this letter and the accompanying Notice are not

subject to the clearance procedures of the Office of Management and not

Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.

We will gladly discuss any questions you have concerning this inspection.

Sincerely,

" Original Signed by i:. W. C:or-- E"h

Hubert J. Miller, Director

Division of Reactor Safety

Enclosures:

1.

Notice of Violation

2.

Inspection Reports

No. 50-373/89010(DRS);

No. 50-374/89010(DRS)

cc w/ enclosures:

T. Kovach, Nuclear

Licensing Manager

G. J. Diederich, Station

Manager

DCD/DCB (RIDS)

Licensing Fee Management Branch

Resident Inspector, RIII

Richard Hubbard

J. W. McCaffrey, Chief, Public

Utilities Division

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RII

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Commonwealth Edison Cotepany

3

JUN 2 81989

<

i.i -

Distribution Cont'd

David Rosenblatt, Governor's

Office of Consumer Services

,

Commissioner'Curtiss, OCM/JC

K. Hart, NRR/LPEB

Director / Division of Reactor

Safety RI, RII, RIV, RV

.

i

22._ . _-._