ML20205P123
| ML20205P123 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/12/1986 |
| From: | Jaudon J, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20205P110 | List: |
| References | |
| 50-298-86-07, 50-298-86-7, NUDOCS 8605210166 | |
| Download: ML20205P123 (6) | |
See also: IR 05000298/1986007
Text
-a
. .
APPENDIX B
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC 'nspection Report:
50-298/86-07
License:
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:
F ruary 24-28 1986
Inspector-
A4/
/
8d
~
9. M elll, PNject Engineer, Project
Date
S ect n A, Reactor Projects Branch
Approved:
/1//
[///l
C/
P Jau
n, Chief! Pr6je~ct Section A,
Dat'e
R cto Projects Branch
Inspection Summary
I
Inspection Conducted February 24-28, 1986 (Report 50-298/86-07)
Areas Inspected:
Routine, announced inspection of the actions taken with regard
to previously identified inspection findings.
Results: Within the area inspected, one deviation was identified (inadequate
preventive action).
8605210166 860516
ADOCK 050002 8
,
'
G
,
I
- - _ _ _ _ _ _ _ - _ - _ _ _ - _ _ _ _ _ . _ _ _ .
a . .
-2-
DETAILS
1.
Per' sons Contacted
,
L. F. Bednar, Senior Staff Engineer
R. D. Brown, I&C Specialist
J. E. Dunn, Records Control Specialist
R. Fentiman, Purchasing Analyst
S. S. Freborg, Lead Mechanical Engineer
C. R. Goings, Regulatory Compliance Specialist
- G. R. Horn, Nuclear Operations Division Manager
J. Larson, QA Engineer (GO)
E. M. Mace, Plant Engineering Supervisor
- J. M. Meacham, Technical Manager
- J. V. Sayer, Technical Staff Manager
G. Smith, Senior QA Specialist
J. Smith, Technical Welding Specialist
G. G. Stuchal, Construction Manager
- P. V. Thomason, Senior Nuclear Advisor
V. L. Wolstenholm, QA Manager
- Denotes personnel attending exit meeting.
2.
Actions on Previously Identified Inspection Findings
(Closed) Violation (298/8501-01):
Failure to detect discrepancies during
vendor documentation reviews.
The licensee established that the documents in question did have incorrect
heat numbers on the heat trace and ultrasonic examination reports.
Licensee corrective actions included verifying traceability of corrected
subvendor documentation based upon the vendors unique " Mill Work Number"
identification system; replacing all incorrect heat trace and ultrasonic
examination reports with corrected reports; QA verification that trace-
ability methods and information was accurate; review of additional heat
trace and ultrasonic examination reports to verify that the problem was
limited to those items listed in the violation; and revision of the
construction management procedure, CMP 8-1-3, to require training of
contract personnel in this area.
The NRC inspector reviewed the above licensee actions and documentation
changes and determined that those immediate and preventive actions were
complete.
This item is closed.
(Closed) Unresolved Item (298/8512-01):
Need to establish a formal method
of incorporating changes to the inservice test program.
-
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _
_ _ -_
______
_ _ _ _
,
, , ,
\\
-3-
The NRC inspector verified that the licenaee revised design change
procedure EP 3.4 to require that changes be reviewed in light of their
impact on the inservice inspection and inservice test programs. The NRC
inspector noted that changes internal to the program were to be handled as
if they were procedure changes. At the time of the inspection, it was
also found that the formal methods of handling these latter type changes
was being reviewed by the licensee because of a licensee nonconfonaance
report.
,
This item is closed.
(Closed) Unresolved Item (298/8512-02):
Preinservice inspection of a
questionable weld.
This item concerned whether or not coverage from both sides of the weld
was possible (as required by the ASME Code,Section XI, Article III - 4420
and4430). The weld in question (RL-A-15 (SW-1)) was ultrasonically
tested by the inservice inspection vendor, General Electric, and this was
documented in General Electric reports to the licensee, which the NRC
inspector reviewed. The weld in question is a 6 inch, branch type
connection to the reactor water clean up system, on a 90 elbow of the 20
inch residual heat removal supply piping. The NRC inspector verified the
ASME Code and the procedure requirements are for one side coverage, as a
mininum, when it is not possible to cover both sides.
This item is closed.
(Closed) Violation (298/8512-03):
Failure to identify a linear
indication.
The licensee subsecuently repaired this weld.
The NRC inspector reviewed
the post repair radiographs and determined that the repairs were
satisfactory.
Licensee preventive action included the requirement that
all radiographs asiociated with the pipe replacement project were to be
reviewed by a CBI JNT-TC-1A level III inspector. The NRC inspector
reviewed and evaluated five radiograph packages in order to verify that
they were reviewed by the level III inspector.
The NRC inspector verified
that a non-qualified CNS individual also reviewed all radiographs. The
individual did have some qualifications. As a result of the CNS review,
some additional rework did occur.
This item is closed.
(Closed)UnresolvedItem(298/8512-04):
Concerns with the vendor's
radiographic program.
The specific welas identified in the NRC Report were 'reradiographed and,
with one exception, indications were verified to be film artifacts. The
exception, field weld N1A, was repaired. Audits by outside consultants,
i.e., Lambert and Hartford Steam Boiler Inspection & Insurance were
performed to upgrade and improve the CBI radiographic program. A review
i
.
a . .
-4-
of later CBI radiographs by the NRC inspector found double film loading,
clearer interpreter recording and documentation of indications, and
greater film sensitivity.
This item is closed.
(Closed) Violation (298/8520-03):
Failure to impose 10 CFR Part 21 in
The licensee has established procedures which require that 10 CFR Part 21
be incorporated into purchase orders (P0s) for components identified as
" essential." The NRC inspector reviewed 15 current P0s and verified that
all " essential" component P0s had Part 21 incorporated.
However, he noted
that some P0s associated with design change DC 86-21 (the alternate
shutdown modification) were not identified as essential and, therefore,
Part 21 was not incorporated into there P0s.
The P0s in question included
instrumentation such as high pressure coolant injection turbine steam
inlet pressure (HPCI-PI-1111), torus level (PC-LI-110), residual heat
removal flow indication (RHR-FI-11338), reactor vessel level
instrumentation (NBI-LI-191B), and level instrument (NBI-LI-1858).
The
licensee stopped further processing of the aforementioned P0s until the
instruments are correctly classified as " essential" or " nonessential."
The NRC inspector reviewed the licensee's equipment classification
procedure, EP 3.13 " Equipment Classification." He noted that fire
protection equipment could be classified as " essential" or " nonessential"
because of ambiguous procedure wording.
This item is unresolved pending:
(1) correct classification of the
identified instruments, and (2) review and revision of procedure EP 3.13
to rid it of ambiguities in the area of fire protection equipment
(298/8607-01).
The preventive action designed to be taken by the licensee in this area
was to increase training of engineering personnel involved with
procurement of safety-related equipment.
The training records were
reviewed by the NRC inspector, and it was noted that a new employee and
some senior general office (corporate level) employees were not trained on
this subject.
This finding was similar to an observation that was
documented in NRC report (50-298/86-06).
This was identified as a
deviation (298/8607-02).
This item is closed.
(Closed) Unresolved Item (298/8520-04):
Apparent misuse of a heat
treatment test block.
The NRC inspector found that the licensee established that one of the
certified material test reports (CMTR) in question was in error.
The
error was made by a subvendor's representative.
A corrected CMTR has been
received.
The NRC inspector verified that the corrected CMTR was in the
Purchase Order (PO) files.
.
. .
-5-
This item is closed.
(Closed) Open Item (298/8204-04):
Revision of procedures on establishing
~
.-
,
quality classifications.
Licensee Administrative Procedure No.1.11 was replaced by new
procedures AP 1.4, 1.5, 1.7, and 1.8.
Additionally, procedure EP 3.13
was issued. This procedure is more specific in the classifing components
than was procedure QAI-9 and CNS Instruction Letter No. 75-1, which
'
classified only systems. Essential and equipment ' qualification classifica-
.-
.,
tions are defined in the Itcensee's procedure as requiring 10 CFR Part 21,
>
10 CFR Part 50, Appendix B and ANSI N45.2 on P0s. The licensee's procedure
identifies essential-commerical grade as requiring Appendi_x B and N45.2.
All essential, equipment qualification and essential-commerical grade
procurement are required by procedure to be given receipt inspection.
This item is closed.
(Closed) Open Item (298/8309-03):
Completion of component classification.
This item is similar to the unresolved item opened in this report, and is
addressed with that unresolved item.
This item is closed.
- .-
" (Closed) Open Item (298/8520-01):
Review of design change: records.
The NRC inspector found that the design change file (DC 85-41) was
-
3;
completed and reviewed by the licensee.
He found that the 10 CFR 50.59
review was, completed July 11, 1985, by the licensee and that General
Electric had performed the same analysis on May 8,1985. The completion
-
report was dated August 16, 1985.
This item is closed.
(Closed)OpenItem(298/8520.02): A change to the inservice inspection
program to include replacement jet pump beams.
>
Revisian 3 of the inservice inspection program addresses in part 7.3, the
augmented inservice. inspection. The NRC inspector found that the replace-
ment jet pump besns are to be irspected at a frequency of once during the
second 10-year interval . At the time of this inspection, it was noted
that the inservice inspection program did not list or otherwise identify
each individual jet pump beam reouired to be inspected, nor was the
ultrasonic test procedure listed that would be used to perform the
.,
inspection of those components.
This item is closed.
-
d
d
o'..
-6-
3.
Unresolved Items
Unresolved items are matters about which more information is required in
order to ascertain whether or not the items are acceptable, violations, or
deviations.
The following unresolved item was discussed in this report:
Paragraph
Item
Subject
2
8607-01
Classification of the
Alternate Shutdown System
4.
Exit Meeting
The NRC inspector conducted an exit meeting on February 28, 1986, with the
licensee personnel denoted in paragraph 1.
The NRC senior resident
inspector also attended. At this meeting, the scope and findings of the
inspection were summarized.
\\