ML20235M517
| ML20235M517 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/17/1989 |
| From: | Barnes I, Gilbert L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20235M500 | List: |
| References | |
| 50-285-89-08, 50-285-89-8, NUDOCS 8902280287 | |
| Download: ML20235M517 (4) | |
See also: IR 05000285/1989008
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APPENDIX B
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U.S. NUCLEAR REGULATORY-COMMISSION
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REGION IV
NRCInspeciion' Report:!'50-285/89-08
Operating License:
Docket:
50-285
Licensee:-.0maha Public Power District (0 PPD).
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'FacilityName:'.FortCalhounStation(FCS)
Inspection At: . FCS, Blair, Nebraska
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Inspection Conducted:
February 6-10, 1989
Inspector:
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L. D. . Gilbert, Reactor Inspector,. Materials
Date
and Quality Programs Section, Division of
Reactor Safety
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I. Barnes, chief, Materials and Quality . .
Date
Programs Section, Division of Reactor Safety
Inspectiott, Summary
Inspection' Conducted February 6-10, 1989 (Report 50-785/89-08)
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~ Areas Inspected:. Routine, unannounced inspection of licensee's action on
previous inspection findings.
Theinspection'confirmedthatappropriatecorrectiveactions'(i.e.,
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Results:1
reradiography) had been taken to resolve prior inspection findings concerning
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the~ radiographic examination of the emergency feedwater storage tank by
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Professional Services Inc. The inspection identified, however, that
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additional noncompliance with ASME Code requirements had been noted during
review'of other radiographs produced by.this contractor with respect-to welds
in safety-related modifications. No corrective actions had been taken in.
response to these nonconformances. The licensee had also previously informed
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the NRC'that review of 1987 modifications had found that radiographs and
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techniques used were of acceptable quality. Two violations were identified
.(paragraph 2) as-a result of the failure to take corrective action and the
providing of inaccurate information to the NRC.
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8902280287 890217 U
ADOCK 05000285
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DETAILS
1.
Persons Contacted
- J.' H. MacKinnon, Acting Division Manager, Nuclear Operations
W. G. Gates, Plant Manager
- T. J. McIver, Manager, Nuclear Projects
- D. W. Dale, Supervisor, Quality Control (QC)
- D. J. Matthews, Supervisor, Nuclear Licensing
- R. Kellogg, Supervisor, Special Services
- A. W. Richard, Manager, Quelity Assurance (QA)
- R. L. Jaworski, Manager, Station Engineering
J. L. Dyer, Senior Quality Control Inspector
C. Bloyd, Lead, Special Services Engineer
Hartford Steam Boiler Inspection and Insurance Company
J. Tetreault. Authorized Nuclear Inspector
NRC
- P. Harrell, Senior Resident Inspector
- R. P. Mullikin, Project Engineer
The NRC inspector also interviewed other licensee employees during the
inspection.
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- Denotes attendance at exit interview conducted on February 10, 1989.
2.
Followup of Previously Identified Items
a.
Unresolved Item (92701)-
the emergency feedwater storage tank (EFWST) graphic examination o
(Closed)UnresolvedItem 285/88?9-01:
Radio
is considered an
unresolved item pending acceptable radiographs and NRC review after
the EFWST has been repaired and reradiographed 100 percent. The NRC
inspector selected four welds from the EFWST for review following
repair and 100 percent reradiography of the EFWST welds by EBASCO.
The radiographs showed evidence of repair and were of acceptable
quality including radiographic technique.
This item is resolved.
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b.
Deviations
(92702)
(Closed)DeviationP85/8831-01:
Failure to meet commitments to
provide an engineering guide for the preparation of welding
procedures. An engineering guide for preparing welding procedure
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specifications has been prepared which was issued on
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October 26, 1988, as Civil Engineering Instruction'(CEI) 6..
Selected engineering, QC and nuclear production personnel were
trained on the guidance. .The OPPD tracking ' system for action
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tracking of commitments to the Commission was reviewed by the NRC
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inspector. The tracking system action overdue dates were discussed
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with plant and corporate licensing personnel.to. assure that the
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commitments to NRC had been met. The licensing personnel confirmed
that the commitments to NRC had been completed and the system was
being used to track internal actions due OPPD Nuclear Licensing as a
followup to the NRC commitment. This item is closed.
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'(Closed) Deviation-785/8831-0$:.Failuretomeetcommitmentsto
reradiograph the repair welds made to the EFWST. The licensee
contracted EBASCO to review the radiographs produced by Professional
Services Incorporated (PSI) 'for all the safety related modifications
installed during the 1983, 1984, 1985 and'1987 outages.' The EBASCO
review identified problems with both acceptability'of radiographer
areas and compliance of radiographs to the Code. These problems
related to radiographic examination,of the repairs to the EFWST ' welds
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as well as other radiographic examinations performed by PSI on the
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pressurizer spray piping during the.1987 refueling outage. The
results of the EUASCO review was included in a Operations Support
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' Analysis Report (0SAR) No. 88-53 which was an analysis to determine
-if the radiographic examination technique employed by PSI at the Fort
Calhoun Station.could create a substantial safety. hazard. The
engineering analysis concluded that the radiographic examinations
which did not meet Code requirements would not create a substantial.
safety hazard. The engineering ' analysis stated that reradiography of
the EFWST should be perfonned in order to. address the numerous
concerns identified with the tank. . The NRC inspector selected.four
welds from the EFWST for review following repair and'100 percent
reradiography. The welds selected-included a longitudinal ' seam weld,
a circumferential' seam weld, and two nozzle welds. The welds were
radiographer for 100 percent of the length by EBASCO and areas
repaired were reradiographed. Approximately.70 final radiographs
were reviewed and were consistent with the radiographic technique and
acceptance' criteria of ERASCO Procedure RT-2002 which incorporated
the radiographic examination requirements of ASME B&PV Code
Section III, Subsection ND5000, 1983' Edition through Summer 1984
Addenda. This item is closed.
However, the NRC inspector identified two concerns relating to the
generic review of radiography performed by PSI and the identification
of nonconforming radiographs of Code Class I welds in the pressurizer
spray piping system.
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First, nonconforming conditions were identified by EBASCO in the
radiographic examination performed on the pressurizer spray piping as
stated in Operations Support Analysis Report (OSAR) No. 88-53 and
other radiography nonconforming conditions were identified by an
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OPPD contract QC Level III engineer in a memorandum to Oc s'upervision
with copies to QA and Engineering. The engineering evaluation of the
nonconformances identified by ERASCO were determined to not be a
significant safety. hazard for continued operation with no'further
radiography required.
However, the Code.of Federal Regulations
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requires that systems and components of pressurized water-cooled
nuclear power reactors must meet the requirements of the ASME-Boiler
and' Pressure Vessel. Code. The nonconforming conditions identified by
EBASCO and QC were not corrected to meet Code requirements or
documented in a nonconformance report as required by Standing Order
No..G-18.
This is an apparent violation for failure to take
appropriate corrective action to correct nonconforming conditions.
(285/8908-01)
Second,.the licensee's response to NRC Inspection Report No. 88-31
'for Deviation 285/8831-02 stated that results of the review of
modifications installed in the 1987 outage showed that the radiographs
and techniques used were of acceptable' quality.
However, as stated
above, the review by EBASCO and QC identified radiographs of welds in
the pressurizer spray piping that did not meet Code requirements for
technique and quality. This is an apparent violation for providing
the NRC with inaccurate information.
(285/8908-02)
. 4.
Exit Interview
An exit interview was conducted on February 10, 1989, with those personnel
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denoted.in paragraph 1.
At the exit interview, the NRC inspector informed '
the licensee that three previously identified inspection finding would be
closed, that the failure to provide appropriate corrective action and
nonconformance reports would be.an apparent violation, and that the
inaccurate information provided in a response to NRC would be discussed
further with NRC management. No'information was presented to the NRC
inspector that was identified by the licensee as proprietary.
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