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{{#Wiki_filter:_ __ ____---_--- - ----- - -- - ~ ~                 ~
{{#Wiki_filter:_ __ ____---_--- - ----- - -- - ~ ~
  ,
~
    y
yy
      yy              q
,
  , j
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    o                R
q
                      j                       UNITED STATES
UNITED STATES
                                    NUCLEAR REGULATORY COMMISSION
j
                                            WASHINGTON, D.C. 20555 0001
j
        . . . . . ,o
NUCLEAR REGULATORY COMMISSION
                                                    May 6, 1998
,
        Mr. Oliver D. Kingsley, President
o
        Nuclear Generation Group
R
        Attn.: Regulatory Services
WASHINGTON, D.C. 20555 0001
        Commonwealth Edison Company
. . . . . ,o
        Executive Towers West lll
May 6, 1998
        1400 Opus Place, Suite 500                                                                               {
Mr. Oliver D. Kingsley, President
        Downers G' rove, IL 60515
Nuclear Generation Group
        SUBJECT:
Attn.: Regulatory Services
                        QUAD CITIES NUCLEAR POWER STATION - DESIGN IN
Commonwealth Edison Company
                        INSPECTION REPORT NOs. 50-254/98-201 and 50-265/98-
Executive Towers West lll
        Dear Mr. Kingsley:
1400 Opus Place, Suite 500
        From February 16 through March 27,1998, the staff of the U.S. Nuclear Reg
{
        Commission (NRC), Office of Nuclear Reactor Regulation (NRR) Special insp                     ,
Downers G' rove, IL 60515
      The team selected for inspection the residual heat
SUBJECT:
      systems along with the RHR service water (RHRSW) and the automatic dep
QUAD CITIES NUCLEAR POWER STATION - DESIGN IN
      support systems. The purpose of the inspection was to evaluate the capability of the
INSPECTION REPORT NOs. 50-254/98-201 and 50-265/98-
      systems to perform safety functions required by their design bases, the adherence to it                    '
Dear Mr. Kingsley:
      design and licensing bases, and the consistency of the as-built configuration a
From February 16 through March 27,1998, the staff of the U.S. Nuclear Reg
      operations with the updated safety analysis report (USAR).
Commission (NRC), Office of Nuclear Reactor Regulation (NRR) Special insp
                                                                                                                  !
The team selected for inspection the residual heat  
      The results of the inspection were discussed during a public exit on                 ,
,
                                                                                                March
systems along with the RHR service water (RHRSW) and the automatic dep
                                                                                              and are
support systems. The purpose of the inspection was to evaluate the capability of the
                                                                                                          27,1998
systems to perform safety functions required by their design bases, the adherence to t
      presented in the enclosed report. Several team findings, as discussed below and i
i
      significantly challenged the capability of the systems to perform their comp
design and licensing bases, and the consistency of the as-built configuration a
                                                                                                        ,
'
      basis accident mitigation actions. Where appropriate, your staff took immediate cor
operations with the updated safety analysis report (USAR).
      of the issues prior to restarting the units. compensatory actions to ensure s
The results of the inspection were discussed during a public exit on March 27,1998
      (ECCS) relies on containment overpressure to ensure p                                   .
!
      Reliance on overpressure has significantly increased since originalg-                                design an
presented in the enclosed report. Several team findings, as discussed below and  
      discussed between your staff and the NRC. Additional                                               4
and are
                                                                                                            j
,
    several operator actions that were not consistent with instructions provided in th
significantly challenged the capability of the systems to perform their comp
    operating procedures (EOP)s. Revision of the EOP instructions to the operator to make                         ;
,
    consistent with the analysis assumptions is essential to ensure adequate NPSH is ava!
basis accident mitigation actions. Where appropriate, your staff took immediate co
    under accident
of the issues prior to restarting the units. compensatory actions to ensure s
    restarting  the units. conditions. Your staff has scheduled completion of EOP revisions prio
(ECCS) relies on containment overpressure to ensure p
                                                                                                          K;       I
Reliance on overpressure has significantly increased since original design a
.
discussed between your staff and the NRC. Additional
g-j
several operator actions that were not consistent with instructions provided in th
4
operating procedures (EOP)s. Revision of the EOP instructions to the operator to make
;
consistent with the analysis assumptions is essential to ensure adequate NPSH is ava!
under accident conditions. Your staff has scheduled completion of EOP revisions prio
K;
I
restarting the units.
1
1
                                                                                                                    I
I
      9805180370 980506
9805180370 980506
      PDR     ADOCK 05000254
PDR
      0                       PDR       c
ADOCK 05000254
l                                                                                                 _______________A
0
PDR
c
l
_______________A


      - _ - _ - _ - - _ _ _ - _ -__ _ _ - _ ___                                                             _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - _ _ - _ _ -
- _ - _ - _ - - _ _ _ - _ -__ _ _ - _ ___
  .
_ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - _
  9l
_ - _ _ -
                                                Oliver D. Kingsley .                     -2-
.
                                                Errors in the assumptions provided to your fuel vendors for the loss of coolar,t (LOCA) analysis .
9l
                                            ' resulted in an increase of fuel peak clad temperature (PCT) by an estimated 60* F. While the
Oliver D. Kingsley .
                                                PCT for QC remains well below the 2200* F limit, additionalincreases would occur if the LOCA
-2-
                                                analysis considered instrument uncertainty for assumed emergency core cooling system
Errors in the assumptions provided to your fuel vendors for the loss of coolar,t (LOCA) analysis .
                                                performance. Your staff has indicated a desire to hold discussions with the NRC staff to
' resulted in an increase of fuel peak clad temperature (PCT) by an estimated 60* F. While the
                                                resolve the need to consider instrument uncertainty in your LOCA analysis.
PCT for QC remains well below the 2200* F limit, additionalincreases would occur if the LOCA
L                                               Two examples were identified where, under worst case environmental design conditions,'
analysis considered instrument uncertainty for assumed emergency core cooling system
P                                                                                                                                                                   j
performance. Your staff has indicated a desire to hold discussions with the NRC staff to
                                                current installed equipment performance was questionable, in the first example, during a                           j
resolve the need to consider instrument uncertainty in your LOCA analysis.
L                                               postulated downstream Dam-14 failure, the thermal performance of the ultimate heat sink
L
                                                (UHS) was not assured. Additionally, the recently implemented technical specification (TS) for
Two examples were identified where, under worst case environmental design conditions,'
                                                the UHS does not ensure adequate UHS thermal performance ~ capability. In the second case,-
j
                                              current RHR heat exchanger thermal capacity and material condition, in combination with
P
current installed equipment performance was questionable, in the first example, during a
j
L
postulated downstream Dam-14 failure, the thermal performance of the ultimate heat sink
(UHS) was not assured. Additionally, the recently implemented technical specification (TS) for
the UHS does not ensure adequate UHS thermal performance ~ capability. In the second case,-
current RHR heat exchanger thermal capacity and material condition, in combination with
questionable RHRSW system flow performance challenges the system's heat removal
capability under extreme Mississippi River conditions.
'
'
                                              questionable RHRSW system flow performance challenges the system's heat removal
As a result of the pump impeller modification, the brake horse power (BHP) for the RHRSW
                                              capability under extreme Mississippi River conditions.
l
                                            As a result of the pump impeller modification, the brake horse power (BHP) for the RHRSW
pump increased; your staff incorrectly calculated a decrease in BHP. This error resulted in an
l                                             pump increased; your staff incorrectly calculated a decrease in BHP. This error resulted in an
increase in emergency diesel generator (EDG) load above the 2000 hr/yr rating for the 1/2 -
                                              increase in emergency diesel generator (EDG) load above the 2000 hr/yr rating for the 1/2 -
EDG. ' Resolution of this item has resulted in your staff identifying that manually applied EDG
                                              EDG. ' Resolution of this item has resulted in your staff identifying that manually applied EDG
loads are not well understood or procedurally controlled. Procedure changes and additional
;
;
                                            loads are not well understood or procedurally controlled. Procedure changes and additional
!
!                                            evaluations of EDG loading are ongoing.                       "
evaluations of EDG loading are ongoing.
"
i
i
i
i
                                            The team found deficiencies in testing and surveillance activities at the plant. For example, the
The team found deficiencies in testing and surveillance activities at the plant. For example, the
l
l
                                            EDG load sequence timing relay setpoint verification did not assure TS limits were maintained.                         j
EDG load sequence timing relay setpoint verification did not assure TS limits were maintained.
j
-
The GL 89-13 testing of the RHR heat exchangers did not consider instrument uncertainty,
i
;
;
-
allowed preconditioning by reverse flow, and allowed acceptance of degraded conditions -
                                            The GL 89-13 testing of the RHR heat exchangers did not consider instrument uncertainty,                                i
l
                                            allowed preconditioning by reverse flow, and allowed acceptance of degraded conditions -
without strict administrative controls. The use ofinstalled plant equipment to satisfy ASME test
l                                           without strict administrative controls. The use ofinstalled plant equipment to satisfy ASME test
!
!
                                            equipment accuracy requirements was not properly evaiuated or documented. Also, the
equipment accuracy requirements was not properly evaiuated or documented. Also, the
                                            corrective actions for previously identified questions associated with the thermal capacity of the
corrective actions for previously identified questions associated with the thermal capacity of the
l                                          RHR heat exchanger were not timely.
RHR heat exchanger were not timely.
                                          The team noted design program weaknesses, including updating and control of calculations,
l
                                    . and nonconservative assumptions and inputs to calculations. In addition, the team identified
The team noted design program weaknesses, including updating and control of calculations,
                                          discrepancies and inconsistencies in the UFSAR, procedures, calculations, drawings, and other
. and nonconservative assumptions and inputs to calculations. In addition, the team identified
!                                          documents.
discrepancies and inconsistencies in the UFSAR, procedures, calculations, drawings, and other
,                                          Your engineering staff exhibited adequate knowledge of their systems and provided excellent                            .
!
!
                                    . support to the inspection team. Subsequent to NRC announcement of the inspection, the QC
documents.
p                                          review of the systems selected by the team identified many good issues which are currently
Your engineering staff exhibited adequate knowledge of their systems and provided excellent
l                                          being resolved by your corrective action program.
,
,:                                         Please provide a schedule, within 60 days, detailing your plans to complete the corrective
.
                                          actions for the open items listed in Appendix A to the enclosed report. This schedule wi!!
!
                                          enable the NRC staff to plan for the reinspection and closeout of these items.
. support to the inspection team. Subsequent to NRC announcement of the inspection, the QC
review of the systems selected by the team identified many good issues which are currently
p
being resolved by your corrective action program.
l
,:
Please provide a schedule, within 60 days, detailing your plans to complete the corrective
actions for the open items listed in Appendix A to the enclosed report. This schedule wi!!
enable the NRC staff to plan for the reinspection and closeout of these items.
!
!
!
!


                                              _
_
                                                                      _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ _
_ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ _
  .
.
  %
%
    Mr. Oliver Kingsley                               -3-
Mr. Oliver Kingsley
-3-
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l
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l
'    As with all NRC inspections, we expect that your staff will evaluate the applicability of the
As with all NRC inspections, we expect that your staff will evaluate the applicability of the
    results and specific findings of this inspection to other systems and components throughout the
'
    plant. In addition, please evaluate the inspection findings, both specific and programmatic,
results and specific findings of this inspection to other systems and components throughout the
plant. In addition, please evaluate the inspection findings, both specific and programmatic,
against your response to the NRC's October 9,1996, request for information pursuant to 10
!
!
    against your response to the NRC's October 9,1996, request for information pursuant to 10
CFR 50.54 (f) regarding the adequacy and availability of design basis information.
    CFR 50.54 (f) regarding the adequacy and availability of design basis information.
;
;
l
l
    In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the
    NRC Public Document Room. NRC Region til via separate correspondence will handle any
NRC Public Document Room. NRC Region til via separate correspondence will handle any
    enforcement action resulting from this inspection. Should you have any questions conceming
enforcement action resulting from this inspection. Should you have any questions conceming
    the enclosed inspection report, please contact the project manager, Mr. R. M. Pulsifer at
the enclosed inspection report, please contact the project manager, Mr. R. M. Pulsifer at
    (301) 415-3016, or the inspection team leader, Mr. M. W. Branch, at (301) 415-1279.
(301) 415-3016, or the inspection team leader, Mr. M. W. Branch, at (301) 415-1279.
                                                    Sincerely,
Sincerely,
                                                    Jo E5 F. Stolz, Chief
Jo E5 F. Stolz, Chief
                                                      ents Assessment, G neric Communications,
ents Assessment, G neric Communications,
                                                    and Special inspection Branch
and Special inspection Branch
                                                    Division of Reactor Program Management                                         l
Division of Reactor Program Management
                                                    Office of Nuclear Reactor Regulation                                           j
l
    Docket Nos.: 50-254 and 50-265
Office of Nuclear Reactor Regulation
j
Docket Nos.: 50-254 and 50-265
l
,
,
                                                                                                                                    l
Enclosure: Inspection Reports 50-254/98-201
    Enclosure: Inspection Reports 50-254/98-201
and 50-265/98-201
                                and 50-265/98-201
cc w/ Enclosure: See next page
    cc w/ Enclosure: See next page
i
                                                                                                                                    i
                                                                                                                                    !
t
t
                                                                                                                                    I
l
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1
1
Line 173: Line 211:
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!
!
                                                                                                                                __~
__~


      _ _ - _ - _ - - _ _ _ - _ - - - _ - .                                           _ _ _ - -             ._                   --   -
_ _ - _ - _ - - _ _ _ - _ - - - _ - .
    t
_ _ _ - -
._
--
-
t
L
L
    .
.
;                                              O. Kingsley                                     Quad Cities Nuclear Power Station           I
O. Kingsley
                                                                                                                                          .
Quad Cities Nuclear Power Station
l                                              Commonwealth Edison Company.                           Units 1 and 2
;
.
l
l
                                                cc:
Commonwealth Edison Company.
l                                               Michael 1. Miller, Esquire                             Vice President - Law and
Units 1 and 2
l                                               Sidley and Austin                                       Regulatory Affairs
l
!                                              One First National Plaza                              MidAmerican Energy Company
cc:
[                                              Chicago, Illinois 60603                                One River Center Place
l
                                                                                                      106 E. Second Street
Michael 1. Miller, Esquire
                                                Commonwealth Edison Company                            P.O. Box 4350
Vice President - Law and
                                              . Quad Cities Station Manager                                                                l
l
                                                                                                      Davenport, Iowa 52808
Sidley and Austin
l                                              22710 206th Avenue N.
Regulatory Affairs
l                                              Cordova, Illinois 61242-9740                          Commonwealth Edison Company -
l                                                                                                    Site Vice President - Quad Cities
!                                              U.S. Nuclear Regulatory Commission                    22710 206th Avenue N.
!
!
                                              Quad Cities Resident inspectors Office                 Cordova, Illinois 61242-9740
One First National Plaza
                                              22712 206th Avenue N.
MidAmerican Energy Company
                                              Cordova, Illinois 61242                               Document Control Desk-Licensing -
[
                                                                                                      Commonwealth Edison Company
Chicago, Illinois 60603
                                              Chairman                                             -1400 Opus Place, Suite 400
One River Center Place
l                                             Rock Island County Board                               Downers Grove, Illinois 60515         l
106 E. Second Street
                                                of Supervisors
Commonwealth Edison Company
P.O. Box 4350
. Quad Cities Station Manager
Davenport, Iowa 52808
l
22710 206th Avenue N.
l
Cordova, Illinois 61242-9740
Commonwealth Edison Company -
l
Site Vice President - Quad Cities
!
U.S. Nuclear Regulatory Commission
22710 206th Avenue N.
!
Quad Cities Resident inspectors Office
Cordova, Illinois 61242-9740
22712 206th Avenue N.
Cordova, Illinois 61242
Document Control Desk-Licensing -
Commonwealth Edison Company
Chairman
-1400 Opus Place, Suite 400
l
Rock Island County Board
Downers Grove, Illinois 60515
of Supervisors
1504 3rd Avenue .
Mr. David Helwig
'
'
                                              1504 3rd Avenue .                                      Mr. David Helwig
Rock Island County Office E dg.
                                              Rock Island County Office E dg.                       . Senior Vice President '
. Senior Vice President '
                                              Rock Island, Illinois 61201                           Commonwealth Edison Company
Rock Island, Illinois 61201
Commonwealth Edison Company
i
i
                                                                                                      Executive Towers West lli
Executive Towers West lli
                                              Illinois Department of Nuclear Safety                 1400 Opus Place, Suite 900
Illinois Department of Nuclear Safety
                                              Office of Nuclear Facility Safety '                   Downers Grove, IL 60515
1400 Opus Place, Suite 900
                                              1035 Outer Park Drive
Office of Nuclear Facility Safety '
                                              Springfield, Illinois 62704                           Mr. Gene H. Stanley
Downers Grove, IL 60515
                                                                                                      PWR's Vice President
1035 Outer Park Drive
                                              Regional Administrator                                 Commonwealth Edison Company
Springfield, Illinois 62704
                                            ' U.S. NRC, Region 111                                   Executive Towers West ill
Mr. Gene H. Stanley
                                              801 Warrenville Road                                   1400 Opus Place, Suite 900
PWR's Vice President
                                              Lisle, Illinois 60532-4351                             Downers Grove, IL 60515
Regional Administrator
                                              William D. Leach                                       Mr. Steve Perry
Commonwealth Edison Company
                                              Manager- Nuclear                                       BWR's Vice President
' U.S. NRC, Region 111
i                                             MidAmerican Energy Company                             Commonwealth Edison Company
Executive Towers West ill
                                            . 907 Walnut Street                                       Executive Towers West lli
801 Warrenville Road
                                              P.O. Box 657                                           1400 Opus Place, Suite 900
1400 Opus Place, Suite 900
                                              Des Moines, Iowa 50303                                 Downers Grove, IL 60515
Lisle, Illinois 60532-4351
Downers Grove, IL 60515
William D. Leach
Mr. Steve Perry
Manager- Nuclear
BWR's Vice President
i
MidAmerican Energy Company
Commonwealth Edison Company
. 907 Walnut Street
Executive Towers West lli
P.O. Box 657
1400 Opus Place, Suite 900
Des Moines, Iowa 50303
Downers Grove, IL 60515
L
L
                                                                                                      Mr. Dennis Farrar
Mr. Dennis Farrar
                                                                                                      Regulatory Services Manager
Regulatory Services Manager
  ;
Commonwealth Edison Company
                                                                                                    Commonwealth Edison Company
;
                                                                                                      Executive Towers West 111
Executive Towers West 111
                                                                                                      1400 Opus Place, Suite 500
1400 Opus Place, Suite 500
                                                                                                      Downers Grove,IL 60515
Downers Grove,IL 60515


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l       O. Kingsley                                       Quad Cities Nuclear Power Plant
-2-
j       Commonwealth Edison Company                       Units 1 and 2
l
        Ms. Irene Johnson, Licensing Director -
l
!       Nuclear Regulatory Services
O. Kingsley
        Commonwealth Edison Company
Quad Cities Nuclear Power Plant
        Executive Towers West lli
j
        1400 Opus Place, Suite 500
Commonwealth Edison Company
        Downers Grove,IL 60515
Units 1 and 2
        Commonwealth Edison Company
Ms. Irene Johnson, Licensing Director -
        Reg. Assurance Supervisor- Quad Cities
!
        22710 206th Avenue N.
Nuclear Regulatory Services
        Cordova, Illinois 61242-9740
Commonwealth Edison Company
        Mr. Michael J. Wallace
Executive Towers West lli
        Senior Vice President
1400 Opus Place, Suite 500
        Commonwealth Edison Company
Downers Grove,IL 60515
      . Executive Towers West 111
Commonwealth Edison Company
        1400 Opus Place, Suite 900
Reg. Assurance Supervisor- Quad Cities
        Downers Grove,IL 60515
22710 206th Avenue N.
                                                                                                                  I
Cordova, Illinois 61242-9740
Mr. Michael J. Wallace
Senior Vice President
Commonwealth Edison Company
. Executive Towers West 111
1400 Opus Place, Suite 900
Downers Grove,IL 60515
I
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  >                    ..
>
>
        DISTRIBUTION:
..
      Docket Files (50-254 & 50-265)
>
              D
DISTRIBUTION:
Docket Files (50-254 & 50-265)
D
PECB R/F
,
,
      PECB R/F
!
!      BSheron
BSheron
      JRoe
JRoe
      JStolz
JStolz
      Inspection Team
Inspection Team
      MBranch
MBranch
      RPulsifer
RPulsifer
      SRichards
SRichards
      DNorkin
DNorkin
      EAdensam
EAdensam
      CRossi, AEOD
CRossi, AEOD
      CMiller, SRI
CMiller, SRI
      HMiller, RI
HMiller, RI
      LReyes, Ril
LReyes, Ril
      ABeach, Rlli
ABeach, Rlli
      EMerschoff, RIV
EMerschoff, RIV
      CHehl, RI
CHehl, RI
    JWiggins, RI
JWiggins, RI
    LPlisco, Ril
LPlisco, Ril
    JJaudon, Ril
JJaudon, Ril
    GGrant, Rlli
GGrant, Rlli
    CPederson, Rlli
CPederson, Rlli
    TGwynn, RIV
TGwynn, RIV
    AHowell, RIV
AHowell, RIV
    ACRS (3)
ACRS (3)
    OGC (3)
OGC (3)
    11S Distribution
11S Distribution
    JRosenthal, AEOD
JRosenthal, AEOD
    ' [4 O C .'' i)
' [4 O C .'' i)
}}
}}

Latest revision as of 21:01, 1 December 2024

Forwards Insp Repts 50-254/98-201 & 50-265/98-201 on 980216-0327.No Violations Noted
ML20247E525
Person / Time
Site: Quad Cities  
Issue date: 05/06/1998
From: Stolz J
NRC (Affiliation Not Assigned)
To: Kingsley O
COMMONWEALTH EDISON CO.
Shared Package
ML20247E528 List:
References
50-254-98-201, 50-265-98-201, NUDOCS 9805180370
Download: ML20247E525 (6)
v • d • e


See also: IR 05000254/1998201

Text

_ __ ____---_--- - ----- - -- - ~ ~

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UNITED STATES

j

j

NUCLEAR REGULATORY COMMISSION

,

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R

WASHINGTON, D.C. 20555 0001

. . . . . ,o

May 6, 1998

Mr. Oliver D. Kingsley, President

Nuclear Generation Group

Attn.: Regulatory Services

Commonwealth Edison Company

Executive Towers West lll

1400 Opus Place, Suite 500

{

Downers G' rove, IL 60515

SUBJECT:

QUAD CITIES NUCLEAR POWER STATION - DESIGN IN

INSPECTION REPORT NOs. 50-254/98-201 and 50-265/98-

Dear Mr. Kingsley:

From February 16 through March 27,1998, the staff of the U.S. Nuclear Reg

Commission (NRC), Office of Nuclear Reactor Regulation (NRR) Special insp

The team selected for inspection the residual heat

,

systems along with the RHR service water (RHRSW) and the automatic dep

support systems. The purpose of the inspection was to evaluate the capability of the

systems to perform safety functions required by their design bases, the adherence to t

i

design and licensing bases, and the consistency of the as-built configuration a

'

operations with the updated safety analysis report (USAR).

The results of the inspection were discussed during a public exit on March 27,1998

!

presented in the enclosed report. Several team findings, as discussed below and

and are

,

significantly challenged the capability of the systems to perform their comp

,

basis accident mitigation actions. Where appropriate, your staff took immediate co

of the issues prior to restarting the units. compensatory actions to ensure s

(ECCS) relies on containment overpressure to ensure p

Reliance on overpressure has significantly increased since original design a

.

discussed between your staff and the NRC. Additional

g-j

several operator actions that were not consistent with instructions provided in th

4

operating procedures (EOP)s. Revision of the EOP instructions to the operator to make

consistent with the analysis assumptions is essential to ensure adequate NPSH is ava!

under accident conditions. Your staff has scheduled completion of EOP revisions prio

K;

I

restarting the units.

1

I

9805180370 980506

PDR

ADOCK 05000254

0

PDR

c

l

_______________A

- _ - _ - _ - - _ _ _ - _ -__ _ _ - _ ___

_ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - _

_ - _ _ -

.

9l

Oliver D. Kingsley .

-2-

Errors in the assumptions provided to your fuel vendors for the loss of coolar,t (LOCA) analysis .

' resulted in an increase of fuel peak clad temperature (PCT) by an estimated 60* F. While the

PCT for QC remains well below the 2200* F limit, additionalincreases would occur if the LOCA

analysis considered instrument uncertainty for assumed emergency core cooling system

performance. Your staff has indicated a desire to hold discussions with the NRC staff to

resolve the need to consider instrument uncertainty in your LOCA analysis.

L

Two examples were identified where, under worst case environmental design conditions,'

j

P

current installed equipment performance was questionable, in the first example, during a

j

L

postulated downstream Dam-14 failure, the thermal performance of the ultimate heat sink

(UHS) was not assured. Additionally, the recently implemented technical specification (TS) for

the UHS does not ensure adequate UHS thermal performance ~ capability. In the second case,-

current RHR heat exchanger thermal capacity and material condition, in combination with

questionable RHRSW system flow performance challenges the system's heat removal

capability under extreme Mississippi River conditions.

'

As a result of the pump impeller modification, the brake horse power (BHP) for the RHRSW

l

pump increased; your staff incorrectly calculated a decrease in BHP. This error resulted in an

increase in emergency diesel generator (EDG) load above the 2000 hr/yr rating for the 1/2 -

EDG. ' Resolution of this item has resulted in your staff identifying that manually applied EDG

loads are not well understood or procedurally controlled. Procedure changes and additional

!

evaluations of EDG loading are ongoing.

"

i

i

The team found deficiencies in testing and surveillance activities at the plant. For example, the

l

EDG load sequence timing relay setpoint verification did not assure TS limits were maintained.

j

-

The GL 89-13 testing of the RHR heat exchangers did not consider instrument uncertainty,

i

allowed preconditioning by reverse flow, and allowed acceptance of degraded conditions -

l

without strict administrative controls. The use ofinstalled plant equipment to satisfy ASME test

!

equipment accuracy requirements was not properly evaiuated or documented. Also, the

corrective actions for previously identified questions associated with the thermal capacity of the

RHR heat exchanger were not timely.

l

The team noted design program weaknesses, including updating and control of calculations,

. and nonconservative assumptions and inputs to calculations. In addition, the team identified

discrepancies and inconsistencies in the UFSAR, procedures, calculations, drawings, and other

!

documents.

Your engineering staff exhibited adequate knowledge of their systems and provided excellent

,

.

!

. support to the inspection team. Subsequent to NRC announcement of the inspection, the QC

review of the systems selected by the team identified many good issues which are currently

p

being resolved by your corrective action program.

l

,:

Please provide a schedule, within 60 days, detailing your plans to complete the corrective

actions for the open items listed in Appendix A to the enclosed report. This schedule wi!!

enable the NRC staff to plan for the reinspection and closeout of these items.

!

!

_

_ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ _

.

%

Mr. Oliver Kingsley

-3-

l

l

As with all NRC inspections, we expect that your staff will evaluate the applicability of the

'

results and specific findings of this inspection to other systems and components throughout the

plant. In addition, please evaluate the inspection findings, both specific and programmatic,

against your response to the NRC's October 9,1996, request for information pursuant to 10

!

CFR 50.54 (f) regarding the adequacy and availability of design basis information.

l

In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the

NRC Public Document Room. NRC Region til via separate correspondence will handle any

enforcement action resulting from this inspection. Should you have any questions conceming

the enclosed inspection report, please contact the project manager, Mr. R. M. Pulsifer at

(301) 415-3016, or the inspection team leader, Mr. M. W. Branch, at (301) 415-1279.

Sincerely,

Jo E5 F. Stolz, Chief

ents Assessment, G neric Communications,

and Special inspection Branch

Division of Reactor Program Management

l

Office of Nuclear Reactor Regulation

j

Docket Nos.: 50-254 and 50-265

l

,

Enclosure: Inspection Reports 50-254/98-201

and 50-265/98-201

cc w/ Enclosure: See next page

i

t

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1

i

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l

!

__~

_ _ - _ - _ - - _ _ _ - _ - - - _ - .

_ _ _ - -

._

--

-

t

L

.

O. Kingsley

Quad Cities Nuclear Power Station

.

l

Commonwealth Edison Company.

Units 1 and 2

l

cc:

l

Michael 1. Miller, Esquire

Vice President - Law and

l

Sidley and Austin

Regulatory Affairs

!

One First National Plaza

MidAmerican Energy Company

[

Chicago, Illinois 60603

One River Center Place

106 E. Second Street

Commonwealth Edison Company

P.O. Box 4350

. Quad Cities Station Manager

Davenport, Iowa 52808

l

22710 206th Avenue N.

l

Cordova, Illinois 61242-9740

Commonwealth Edison Company -

l

Site Vice President - Quad Cities

!

U.S. Nuclear Regulatory Commission

22710 206th Avenue N.

!

Quad Cities Resident inspectors Office

Cordova, Illinois 61242-9740

22712 206th Avenue N.

Cordova, Illinois 61242

Document Control Desk-Licensing -

Commonwealth Edison Company

Chairman

-1400 Opus Place, Suite 400

l

Rock Island County Board

Downers Grove, Illinois 60515

of Supervisors

1504 3rd Avenue .

Mr. David Helwig

'

Rock Island County Office E dg.

. Senior Vice President '

Rock Island, Illinois 61201

Commonwealth Edison Company

i

Executive Towers West lli

Illinois Department of Nuclear Safety

1400 Opus Place, Suite 900

Office of Nuclear Facility Safety '

Downers Grove, IL 60515

1035 Outer Park Drive

Springfield, Illinois 62704

Mr. Gene H. Stanley

PWR's Vice President

Regional Administrator

Commonwealth Edison Company

' U.S. NRC, Region 111

Executive Towers West ill

801 Warrenville Road

1400 Opus Place, Suite 900

Lisle, Illinois 60532-4351

Downers Grove, IL 60515

William D. Leach

Mr. Steve Perry

Manager- Nuclear

BWR's Vice President

i

MidAmerican Energy Company

Commonwealth Edison Company

. 907 Walnut Street

Executive Towers West lli

P.O. Box 657

1400 Opus Place, Suite 900

Des Moines, Iowa 50303

Downers Grove, IL 60515

L

Mr. Dennis Farrar

Regulatory Services Manager

Commonwealth Edison Company

Executive Towers West 111

1400 Opus Place, Suite 500

Downers Grove,IL 60515

.

-

- _ _ .

-

_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _

l'

i

-

l

l'

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-2-

l

l

O. Kingsley

Quad Cities Nuclear Power Plant

j

Commonwealth Edison Company

Units 1 and 2

Ms. Irene Johnson, Licensing Director -

!

Nuclear Regulatory Services

Commonwealth Edison Company

Executive Towers West lli

1400 Opus Place, Suite 500

Downers Grove,IL 60515

Commonwealth Edison Company

Reg. Assurance Supervisor- Quad Cities

22710 206th Avenue N.

Cordova, Illinois 61242-9740

Mr. Michael J. Wallace

Senior Vice President

Commonwealth Edison Company

. Executive Towers West 111

1400 Opus Place, Suite 900

Downers Grove,IL 60515

I

l

!

>

l

>

..

>

DISTRIBUTION:

Docket Files (50-254 & 50-265)

D

PECB R/F

,

!

BSheron

JRoe

JStolz

Inspection Team

MBranch

RPulsifer

SRichards

DNorkin

EAdensam

CRossi, AEOD

CMiller, SRI

HMiller, RI

LReyes, Ril

ABeach, Rlli

EMerschoff, RIV

CHehl, RI

JWiggins, RI

LPlisco, Ril

JJaudon, Ril

GGrant, Rlli

CPederson, Rlli

TGwynn, RIV

AHowell, RIV

ACRS (3)

OGC (3)

11S Distribution

JRosenthal, AEOD

' [4 O C . i)

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