ML19331C134
| ML19331C134 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/25/1980 |
| From: | Konklin J, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19331C128 | List: |
| References | |
| 50-440-80-09, 50-440-80-9, NUDOCS 8008140201 | |
| Download: ML19331C134 (4) | |
See also: IR 05000440/1980009
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U.S. NUCLEAR REGUALTORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports No. 50-440/80-09; 50-441/80-09
Docket Nos. 50-440; 50-441
Licenses No. CPPR-148; CPPR-149
Licensee: The Cleveland Electric Illuminating Company
P.O. Box 5000
Cleveland, OH 44101
Facility Name:
Perry Nuclear Power Plant, Units 1 and 2
Inspection At:
Perry Site, Perry, OH
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June 10-12, 1980
Inspection Conducted:
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Inspector:
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Accompanying Personnel:
R. L. Lee
Approved By:
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Projects Section No. 2
Inspection Summary
Inspection on June 10-12, 1980 (Report No. 50-440/80-09; 50-441/80-09)
Areas Inspected: Status of ongoing site construction activities; licensee
actions relative to resolution of singificant deficiency reported per 10 CFR 50.55(c); licensee actions relative to followup on IE Bulletins and
Circulars. This inspection involved 20 onsite inspector-hours by one NRC
inspector.
Results: Two items of noncompliance were identified (infraction inadequate
procedural requirements, Paragraph 1; deficiency - failure to maintain
records of evaluations, Paragraph 2).
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8008140201
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DETAILS
Persons Contacted
Principal Licensee Employees
- W. Kacer, General Supervising Engineer, CQS
- P. Martin, General Supervising Engineer, PQS
- P. Gibson, Construction QC Supervisor
- E. Riley, Contracts Manager
- L. Hartline, PQA Unit Supervisor
- R. Vondrasek, CQE Unit Supervisor
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- B. Walrath, PQE Unit Supervisor
- G. Ankney, Sr. Licensing Engineer
- H. Putre, Sr. Engineer, NSSS Installation
R. Crofton, CQS Piping Quality Engineer
H. Walls, Senior NDE Administrator
R. Williams, CQS Mechanical Quality Engineer
W. Ware, CQS Civil Quality Engineer
Accompanying NRC Personnel
- R. Lee, Engineering Support Inspector, RIII
- J. Hughes, Perry Resident Inspector, RIII
- Denotes those present at the exit meeting on June 10, 1980.
The inspector also contacted other licensee and contractor employees,
including craftsmen and members of the quality, technical, and engineering
staffs.
Functional or Program Areas Inspected
1.
Ongoing Site Construction Activities
The inspector, the RIII accompanying personnel, and the RIII resident
inspector observed ongoing work activities and equipment status in
the units 1 and 2 containment buildings the units 1 and 2 auxiliary
buildings, the intermediate building, the control complex, and the
fuel handling building.
the
During discussions with craftsmen in the Unit I containment,
inspector learned of a potential problem regarding minimum wall
thickness on the Unit I reactor vessel recirculation nozzle (N-2
nozzle) at the 210 azimuth following modification of the safe-end on
the 210 nozzle. Subsequent discussions with the licensee and review
of documents elicited the following information regarding the matter:
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a.
The licensee was unable to identify any requirements in the
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applicable procedures for measurements of minimum wall thickness
on the N-2 nozzles following the modificiations.
b.
No criteria has been established in the applicable specifications
or procedures for minimum wall thickness on the N-2 nozzles.
c.
The potential minimum wall thickness problem on the 210 nozzle
was identified by a UT technician who was performing a weld
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acceptance UT, not intended as a thickness measurement.
d.
Although the minimum wall thickness problem was discussed in the
Nuclear QA Department monthly report for May 1980, which stated
that the matter is under evaluation by GE/ San Jose, no nonconform-
ance report had been issued at the time of this inspection.
The inspector notified the licensee that the failure to have
adequate procedural requirements, including appropriate acceptance
criteria, for accomplishment of the N-2 nozzle modification work,
is in noncompliance with Criterion V of 10 CFR 50, Appendix B
(50-440/80-09-01; 50-441/80-09-01).
The licensee notified the inspector by telephone on June 18, 1980
that subsequent to the RIII inspection, UT thickness measurements
have been made on the other 19 Unit I and Uni. 2 recirculation
(N-2) nozzles in the area of the modifications and that GE has
determined the wall thicknesses to be adequate for those 19
nozzles.
2.
Review of Licensee Actions Relative to IE Bulletins and Circulars
The inspector reviewed the licensee's handling of IE Bulletins and
Circulars to determine whether the system which has been set up for
evaluating and responding to the IE documents is being effectively
implemented.
Included in the review were discussions with CQS and
licensing personnel, and review of the CEI IE Bulletin Log and the
The inspector reviewed the documentation for selected bulletins and
circulars logged by CEI to determine whether distribution was made to
the appt 4:: ate persons and whether appropriate evaluations were
perfo rmed. During the review, the inspector and CEI licensing personnel
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were unable to find evidence that appropriate evaluations had been
performed for those bulletins and circulars which did not require a
written response to the NRC. Examples include IE Bulletins 79-05,
79-06, 79-08, 79-12, 79-17, 79-21, 79-24, and 79-26, and IE Circulars
79-05, 79-07, 79-10, 79-11, 79-12, 79-13, 79-18, 79-19, 79-22, 79-23,
and 79-24.
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The inspector emphasized to the licensee that IE Bulletins and IE
Circulars are notifications of signficant safety concerns by the NRC
and as such, require an evaluation by the licensee for applicability
and necessary corrective actions, whether or not a written response
to the NRC is required. The inability of the licensee to provide
records of such evaluations is an item of noncompliance with Criterion
XVII of 10 CFR 50, Appendix B.
3.
Corrective Action on Service Water Intake Structures, Reported per
The inspector reviewed the corrective actions taken by the licensee
with regard to fabrication deficiencies which were found in the
service water intake structures and the deficiencies in the S&MC
QA Program which allowed the defective strrctures to be fabricated.
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These deficiencies were reported by the licensee, per 10 CFR 50.55(e),
on January 12, 1979.
During this inspection the inspector held discussions with the li-
censee and reviewed the applicable correspondence, procedures, and
other doucmentation to verify that the defective intake structures
will not be used at Perry; that a new contractor, Chicago Bridge and
Iron, will fabricate the new intake structures to revised procedures;
and that the S&MC QA Program has been changed to eliminate the pre-
vious deficiencies.
Based on the review, the inspector concluded
that appropraite actions have been and are being taken to correct the
reported 10 CFR 50.55(e) deficiency. That item is therefore considered
to be closed.
Exit Interview
The inspector, the RIII accompanying personnel, and the RIII Resident
Inspector met with site representatives (denoted under Persons Contacted)
at the conclusion of the inspection on June 12, 1980. The inspector
summarized the scope and findings of the inspection. The licensee
acknowledged the findings reported herein.
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