ML18065B136
| ML18065B136 | |
| Person / Time | |
|---|---|
| Site: | Palisades |
| Issue date: | 12/30/1997 |
| From: | Richards S NRC (Affiliation Not Assigned) |
| To: | Thomas J. Palmisano CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML18065B137 | List: |
| References | |
| 50-255-97-201, NUDOCS 9801130388 | |
| Download: ML18065B136 (5) | |
See also: IR 05000255/1997201
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
Mr. Thomas J. Palmisano
Site Vice President
Palisades Plant
27780 Blue Star Memorial Highway
Covert, Ml 49043
WASHINGTON, D.C. 20555--0001
December 30, 1997
SUBJECT:
PALISADES PLANT DESIGN INSPECTION (NRC INSPECTION REPORT
NO. 50-255/97-201)
Dear Mr . .Palmisano:
From September 16 through November 14, 1997, the staff of the U.S. Nuclear Regulatory
Commission (NRC), Office of Nuclear Reactor Regulation (NRR), Events Assessments, Generic
Communications and Special Inspection Branch, performed a design inspection of the Safety
Injection (SI) and Component Cooling Water (CCW) systems, and their support systems at the
Palisades Plant. The purpose of the inspection was to evaluate the capability of the selected
systems to perform the safety functions required by their design bases, as well as the adherence
of the systems to their respective design and licensing bases, and the consistency of the as-built
configuration and system operations with the final safety analysis report (FSAR). The team
discussed significant findings of the inspection with your staff during the team exit meeting on
November 14, 1997.
The design basis documents (DBDs) reviewed by the team provided comprehensive design
information. As discussed in the enclosed report, the team concluded that the SI and the CCW
systems were capable of performing their intended safety functions although some discrepancies
were identified regarding adherence of the systems to their design and licensing bases.
The team identified deficiencies in the control and performance of calculations. These
deficiencies involved not updating the calculations when analytical inputs were changed; errors in
some calculations; failure to specify uncertainty values in instrument setpoint calculations; a
calculation which contained inadequate analysis to support the conclusion; and a de short circuit
calculation issued without verifying all input parameters or providing any conclusion on the
acceptability of the de system.
The team identified many inconsistencies between the installed configurations of instrument
tubing and the design basis in the CCW and SI systems. As a result of these inconsistencies,
the team had concerns with potential air entrapment into the instrument sensing lines for the high
and low head SI flow transmitters.
The team had questions on some calculations for which the adequacy of the design basis could
not be verified. For example, no analysis was available to demonstrate that the de loads would
operate at the minimum battery voltage stated in the FSAR; no analysis was available to
demonstrate adequate ac voltage at the 120 volt safety-related loads; and no analysis was
available to demonstrate that the battery could carry all required de loads during a design-basis
accident with the battery chargers cross-connected.
9801130388 971230
ADOCK 05000255
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December 30, 1997
. Please provide* a* schedule, within 6o' days, detajling your plans to tomplete the corrective actions
required to resolve the open items listed in "Appendix A to the enclosed report. This schedule will
enable the NRC staff to plan for the reinspectlon and closeout of these items.
In addition, 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 NRC's request (October 9, 1996) for information pursuant to 1 O CFR
50.54(f) regarding adequacy and availability of design bases information.
- 1n accordance with Title 10, Section 2:790(a) of the Code of Federal Regulations, a copy of this
letter and the en~losure will be placed in the NRC's Public Document Room. Any enforcement
action resulting from this inspection will be handled by NRC Region Ill via separate
- correspondence.
Should you ~ave any questions concerning the enclosed inspection report, please contact the
project manager, Mr. Robert Schaaf at (301) 415-1312, or the inspection team leader, Mr. James
A. Isom, at (301) 415-1109. *
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Docket No.: 50-255
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Sincerely,
Original signed by
Donald P. Norkin FOR
Stuart A. Richards, Chief
Events Assessment, Generic Communications,
and Special Inspection Branch
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Enclosure:
li1~pecti~n Report 50-255/97-201
cc:. see next page
DOCUMENT NAME:*G:\\JAI\\PALRPT.WPD "
To receive a copy* of this document. Indicate In the box: *c.~ = Copy without enclosures. *e* = Copy with enclosures "N" = No *copy
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OFFICE
NAME
DATE
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Thomas J. Palmisano
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December 30, 1997
Please provide a schedule, within 60 days, detailing your plans to complete the corrective actions
required to resolve the open items listed in Appendix A to the enclosed report. This schedule will
enable the NRC staff to plan for the reinspection and closeout of these items.
In addition, 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 NRC's request (October 9, 1996) for information pursuant to 10 CFR
50.54(f) regarding adequacy and availability of design bases information.
In accordance with Title 10, Section 2. 790(a) of the Code of Federal Regulations, a copy of this
letter and the enclosure will be placed in the NRC's Public Document Room. Any enforcement
action resulting from this inspection will be handled by NRC Region Ill via separate
correspondence.
0
Should you have any questions concerning the enclosed inspection report, please conta.ct the
- project manager, Mr. Robert Schaaf at (301) 415-1312, or the inspection team leader, Mr. James
A. Isom, at (301) 415-1109.
Docket No.: 50-255
Sincerely,
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Stuart A. Rich rds, Chief
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Events Assessment, Generic Communications,
and Special Inspection Branch
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Enclosure: Inspection Report 50-255/97-201
cc: see next page
_. * .
Consumers Energy Company
cc:
Mr. Thomas C. Berdine
Palisades Plant
27780 Blue Star Memorial Highway
Covert, Michigan 49043
Mr. Robert A. Fenech, Sr Vice Pres
Nuclear, Fossil, and Hydro Operations
- Consumers Energy Company
212 West Michigan Avenue
Jackson, Michigan 49201
M. I. Miller, *Esquire
Sidley & Austin
54th Floor
One First National Plaza
Chicago, Illinois 60603
Mr. Thomas A. McNish
Vice President & Secretary
Consumers Energy Company *
212 West Michigan Avenue
Jackson, Michigan 49201
Judd L. Bacon, Esquire
Consumers Energy Company
212 West Michigan Avenue
Jackson, Michigan 49201
Regional Administrator,* Region Ill
U.S. Nuclear Regulatory Commission
801 Warrenville Road
Lisle, Illinois 60532-4351
Jerry Sarno
Township Supervisor
Covert Township
36197 M-140 Highway
Covert, Michigan 49043
Office of the Governor
Room 1 - Capitol Building
Lansing, Michigan 48913
Palisades Plant
U.S. Nuclear Regulatory Commission
Resident Inspector's Office
Palisades Plant
27782 Blue Star Memorial Highway
Covert, Michigan 49043
Drinking Water and Radiological
Protection Division
Michigan Department of
Environmental Quality
3423 N. Martin Luther King Jr Blvd
P. 0. Box 30630 CPH Mailroom
Lansing, Michigan 48909-8130
Gerald Chamoff, Esquire
Shaw, Pittman, Potts and Trowbridge
2300 N Street, N. W.
Washington DC 20037
Michigan Department of Attorney
General
Special Litigation Division
630 Law Building
P.O. Box 30212
Lansing, Michigan 48909
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