ML20197K156
| ML20197K156 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/09/1986 |
| From: | Jaudon J, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20197K137 | List: |
| References | |
| 50-298-86-13, NUDOCS 8605200275 | |
| Download: ML20197K156 (7) | |
See also: IR 05000298/1986013
Text
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APPENDIX B
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-298/86-13
License: DPR-46
Docket: 50-298
Licensee: Nebraska Public Power District
P. O. Box 499
Columbus, Nebraska 68601
Facility Name: Cooper Nuclear Station (CNS)
Inspection At: CNS Site, Brownville, Nebraska
Inspection Conducted: April 7-10, 1986
Inspector:
M
M
j 9 8d
I
M./McN 'lT, Projedt Engineer, Project
Dafe'
(gW Se(tio
A, Reactor Projects Branch
Approved:
h
. M
1h
Date '
i
i/. P( Ja on, Chief, Project Section A,
LRedcto Projects Branch
Inspection Summary
Inspection Conducted April 7-10, 1986 (Report 50-298/86-13)
Areas Inspected:
Routine, unannounced inspection of the design, design change
and modifications and actions taken with regard to previously identified
inspection findings.
Results: Within the areas inspected, one violation was identified (failure to
fully implement the design change procedure).
8605200275 860513
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ADOCK 05000298
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DETAILS
1.
Persons Contacted
- R. D. Black, Operations Supervisor
J. Boyd,. Shift Supervisor
S. L. Ernest, Engineer
- J. R. Flaherty, Assistant Plant Engineering Supervisor
R. W. Foust, Lead Fngineer
- M. D. Hamm, Security Supervisor
- H. T. Hitch, Acting Plant Services Manager
- G. R. Horn, Nuclear Operations Division Manager
R. W. Krause, Lead Operations Engineer
- E. M. Mace, Plant Engineering Supervisor
- J. M. Meacham, Technical Manager
- J. V. Sayer, Technical Staff Manager
- G. E. Smith,.QA Specialist
N. E. Unruh, Maintenance Planner / Scheduler
'
- Denotes those present at exit interview.
-The NRC inspector also contacted other plant personnel including
administrative and clerical personnel.
2.
Licensee Action on a Previously Identified Inspection Finding
(Closed) Violation (298/8515-01): Failure to perform an unreviewed safety
question evaluation for installed temporary jumpers.
The licensee has established a new procedure OP-2.0.7, " Plant Temporary
Modifications Control" and revised Procedure EP-3.3, " Station Safety
Evaluations." The NRC inspector found that all temporary modifications
are now required to be reviewed to determine if they create an unreviewed
safety question.
If a safety evaluation is determined to be required then
EP-3.3 establishes the requirements and documentation of such an
evaluation. The NRC inspector verified the above procedures were in place
and being implemented. The verification was by review of the temporary
modification sheets, both open and closed for the present year. The index
of temporary modifications in the control room was reviewed. The NRC
inspector noted that electrical and mechanical jumpers were both
addressed. The inspector found that, when a safety evaluation was
required, it was attached to the temporary modification sheet.
This item is closed.
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3.
Design, Design Change and Modifications
The objective of this part of the inspection was to ascertain that design
changes and modifications which are determined by the licensee to not
require approval by the NRC are in conformance with the requirements of
the Technical Specifications (TS) and 10 CFR Part 50.59.
In this regard,
the TS, the Updated Safety Analysis Report (USAR), the Quality Assurance
Program for Operation Policy Document, Revision 2, dated April 29, 1985,
'
and the following procedures were reviewed by the NRC inspector:
Procedure
Title
Rev. No.
Date
Station Safety Evaluations
3
10/30/85
Station Design Changes
3
12/26/85
In addition, the following field copies of design change packages were
4
inspected:
Design Change No.
Subject
80-084
Noble gas effluent monitors and radiciodine and
particulate sampling equipment
83-003-1
Replacement of essential RTDs and
thennocouples inside containment
L
83-023
HPCI exhaust line vacuum breakers
84-13
Upgrade plant air compressor capacity
84-154
Microswitches and mechanical cams in Yarways.84-173
Nuclear qualified direct current motor
starters
85-44
Local reactor vessel pressure gage
4
Computer print outs of all the open design change packages, open equipment
specification changes, and all design change packages subject to a 10 CFR
Part 50.59 evaluation were examined. The most recent " Annual Operating
'
Report," including 10 CCR 50.59 reports, was reviewed by the NRC
inspector.
The NRC inspector inspected the design change packages to determine if
their review and approval had been completed, if they were in compliance
with established procedures, if applicable operating procedures had been
changed, if surveillance procedures and drawings had been revised, if
applicable testing records were complete, if there had been applicable
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revision to training programs, and if they had been reported under 10 CFR 50.59(b). The NRC inspector found that no significant changes were being
installed during this inspection.
In the 13-year history of this plant,
the NRC inspector found about 1400 design change packages have been issued.
About 300 design changes were in progress. Of these 300, about 25 are
subject to 10 CFR 50.59(b) review. No major design changes requiring prior
NRC approval are in progress presently. The oldest design change packages
requiring installation work date were originally approved in 1980. The
oldest design change package requiring a completion report which is the
final post installation review by design engineer was originally approved
in 1977.
The following four problems were identified in the design change packages
sampled by the NRC inspector.
a.
Design Change No.83-023 installed 10-inch vacuum breakers. The
installation records in the package indicated that the change had been
completed. The Updated Safety Analysis Report, Page VI-4-2, was
revised to reflect this change. However, work item (WI) No. 83-2112
removed the installed vacuum breakers. There was no design change
package to support this WI nor a modification to package 83-023 to
reflect this change. The WI No. 83-2112 did not return the equipment
to its original condition. A weldolet, 90 eibow and flange, were
installed with Change No.83-023, but not removed with WI No. 83-2112.
b.
Design change package for Change No.80-084 ordered replacement of
General Electric and Nuclear Measurements equipment with Kaman
Instrumentation equipment in order to extend the range of noble gas
effluent monitors, and radiciodine and particulate sampling equipment.
In review of this package, it was noted that the impact on operating
and surveillance procedures of this change was not identified.
c.
It was also noted that in regard to design change package 80-084, the
change was almost completely installed, but there was no sign off of
the design engineer's final review prior to implementation on the
" Design Input Checklist," as is required by licensee procedure.
This
review is to assure that all design questions are closed. A noncon-
formance report (NCR) No. 005034 was initiated on this by the
licensee after the NRC inspector identified it.
d.
Design change package for No. 85-44 was found to not have a " Status
Report" although the installation was completed as of August 16, 1985,
and the changed equipment turned over to operations on November 7,
1985. The " Status Report" identifies the drawings, procedures,
training program, USAR, and TS changes to be implemented. The failure
to issue " Status Report" was simultaneously identified by a CNS QA
audit but the audit only identified it as an observation.
The above problems were identified as one apparent violation of the
requirements of procedure EP-3.4.
(8613-01)
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4.
Exit Meeting
The NRC inspector conducted an exit meeting on April 10, 1985, with the
licensee personnel denoted in paragraph 1.
The NRC resident inspector
alsc attended. At this meeting, the scope and findings of the inspection
were sunmarized.
_ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _
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