ML20247E525
| 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) | |
See also: IR 05000254/1998201
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555 0001
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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
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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
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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
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design and licensing bases, and the consistency of the as-built configuration a
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operations with the updated safety analysis report (USAR).
The results of the inspection were discussed during a public exit on March 27,1998
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presented in the enclosed report. Several team findings, as discussed below and
and are
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significantly challenged the capability of the systems to perform their comp
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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
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discussed between your staff and the NRC. Additional
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several operator actions that were not consistent with instructions provided in th
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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
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restarting the units.
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9805180370 980506
ADOCK 05000254
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Oliver D. Kingsley .
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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.
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Two examples were identified where, under worst case environmental design conditions,'
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current installed equipment performance was questionable, in the first example, during a
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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.
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As a result of the pump impeller modification, the brake horse power (BHP) for the RHRSW
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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
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evaluations of EDG loading are ongoing.
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The team found deficiencies in testing and surveillance activities at the plant. For example, the
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EDG load sequence timing relay setpoint verification did not assure TS limits were maintained.
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The GL 89-13 testing of the RHR heat exchangers did not consider instrument uncertainty,
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allowed preconditioning by reverse flow, and allowed acceptance of degraded conditions -
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without strict administrative controls. The use ofinstalled plant equipment to satisfy ASME test
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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.
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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
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documents.
Your engineering staff exhibited adequate knowledge of their systems and provided excellent
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. 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
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being resolved by your corrective action program.
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,:
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.
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Mr. Oliver Kingsley
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As with all NRC inspections, we expect that your staff will evaluate the applicability of the
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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
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CFR 50.54 (f) regarding the adequacy and availability of design basis information.
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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
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Office of Nuclear Reactor Regulation
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Docket Nos.: 50-254 and 50-265
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Enclosure: Inspection Reports 50-254/98-201
and 50-265/98-201
cc w/ Enclosure: See next page
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O. Kingsley
Quad Cities Nuclear Power Station
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Commonwealth Edison Company.
Units 1 and 2
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cc:
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Michael 1. Miller, Esquire
Vice President - Law and
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Sidley and Austin
Regulatory Affairs
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One First National Plaza
MidAmerican Energy Company
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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
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22710 206th Avenue N.
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Cordova, Illinois 61242-9740
Commonwealth Edison Company -
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Site Vice President - Quad Cities
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U.S. Nuclear Regulatory Commission
22710 206th Avenue N.
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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
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Rock Island County Board
Downers Grove, Illinois 60515
of Supervisors
1504 3rd Avenue .
Mr. David Helwig
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Rock Island County Office E dg.
. Senior Vice President '
Rock Island, Illinois 61201
Commonwealth Edison Company
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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
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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
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Mr. Dennis Farrar
Regulatory Services Manager
Commonwealth Edison Company
Executive Towers West 111
1400 Opus Place, Suite 500
Downers Grove,IL 60515
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O. Kingsley
Quad Cities Nuclear Power Plant
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Commonwealth Edison Company
Units 1 and 2
Ms. Irene Johnson, Licensing Director -
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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
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DISTRIBUTION:
Docket Files (50-254 & 50-265)
D
PECB R/F
,
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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)