ML20210A382
| ML20210A382 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/29/1987 |
| From: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Dewease J LOUISIANA POWER & LIGHT CO. |
| References | |
| NUDOCS 8705050076 | |
| Download: ML20210A382 (2) | |
See also: IR 05000382/1986031
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APR 2 91987
In Reply Refer To:
Docket:
50-382/86-31
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Louisiana Power & Light Company
ATTN:
J. G. Dewease, Senior Vice President
Nuclear Operations
N-80-
317 Baronne Street
New Orleans, Louisiana
70160
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Gentlemen:
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Thank you for your letter of' April 3,1987, in response to our letter and
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Notice of Violation dated March 4,1987. We have reviewed your reply and find it
responsive to the concerns raised in our Notice of Violation. We will review
the implementation of your corrective actions during a future inspection to
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determine that full compliance has been achieved and will be maintained.
Sincerely,
S r.cd M
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GAG @
J. E. Gagliardo, Chief
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Reactor Projects Branch
cc:
Louisiana Power & Light Company
ATTN:
G. E. Wuller, Onsite
Licensing Coordinator
P. O. Box B
Killona, Louisiana
70066
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Louisiana Power & Light Company
ATTN:
N. S. Carns, Plant Manager
P. O. Box B
Killona, Louisiana
70066
Middle South Services
ATTN: Mr. R. T. Lally
P. O. Box 61000
New Orleans, Louisiana
70161
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Louisiana Power & Light Company
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Louisiana Power & Light Company
ATTN:
K. W. Cook, Nuclear Safety and
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Regulatory Affairs Manager
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317 Baronne Street
P. O. Box 60340
New Orleans, Louisiana
70160
Louisiana Radiation Control Program Director
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LO U ISI AN A / 317 BARONNE STREET
P. O. BOX 60340
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POWER & LIGHT
NEW ORLEANS, LOUISlANA 70160
(504) 595-3100
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April 3, 1987
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U.S. Nuclear Regulatory Commission
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ATTN: Document Control Desk
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Washington, D.C. 20555
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Subject: Waterford 3 SES
Docket No. 50-382
License No. NPF-38
NRC Inspection Report 86-31
Attached is the Louisiana Power and Light Company (LP&L) response to
Violation Nos. 8631-01 and 8631-02 identified in Inspection Report No.
86-31.
If you have any questions on the response, please contact G.E. Wuller,
operational Licensing, at (504) 464-3499.
Very truly yours,
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K.W. Cook
Nuclear Safety and
Regulatory Affairs Manager
KWC:KLB:ssf
cc:
R.D. Martin, NRC Region IV
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G.W. Knighton, NRC-NRR
J.H. Wilson, NRC-NRR
NRC Resident Inspectors Office
E.L. Blake
W.M. Stevenson
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"AN EQUAL OPPORTUNITY EMPLOYER"
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Attachment to
Sheet 1 of 2
LP&L Response To Violation Nos. 8631-01 and 8631-02
VIOLATION NO. 8631-01
10 CFR 50, Appendix B, Criterion V; and Ebasco Specification - General
Power Piping Requirements, LOU 1564-100, require that quality affecting
activities be prescribed by documented instructions, procedures, or
drawings of a type appropriate to the circumstance and that they be
accomplished in accordance with these instructions, procedures, or
drawings.
Contrary to the above, Station Modification SM-107, Backup Spent Fuel Pool
Cooling System was not accomplished in accordance with instructions,
procedures, and drawings. Listed below are examples of discrepancies
between Ebasco Specification LOU-1564-100 and as-built conditions:
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Pipe Supports FSRR-4004 and CCRR-4521: Lock nuts not engaged per
specifications and Cotter keys not installed properly.
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Pipe Support FSRR-4001: Drawing required lock nut missing.
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Pipe Support FSRR-4010: Drawing required weep hole not drilled.
This is a Severity Level IV violation.
RESPONSE
(1) Reason for the Violation
The support sketches included in the Station Modification Package
(SMP) may have lacked adequate details to assure that supports were
installed in accordance with design requirements.
(2) Corrective Action That Has Been Taken
Supports ins.alled under Station Modification 107 including the four
identified in the inspection report were reinspected and the
deficiencies noted in the reinspection were corrected (refer to
CIWA-030338 & CIWA-032292). The design group has been directed to
provide more detail and clearer directions in future design drawings
for those design packages that relate to installation of supports.
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(3) Corrective Action To Be Taken
No further action is deemed necessary.
(4) Date When Full Compliance Will Be Achieved
The directive was approved on March 27, 1987.
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Attachssnt to
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Sheet 2 of 2
VIOLATION NO. 8631-02
10 CFR 50, Appendix B, Criterion XV and site procedure QP-015-001
Nonconformances and Corrective Actions, require that measures be
established to control materials, parts, or components which do not conform-
to requirements in order to prevent their inadvertent use or installation.
Contrary to the above, the following-two examples of failure to control the
use of nonconforming components were identified.
Documentation on two butt welds, FS-SM-107-M3-FW6 and FS-SM-107-M4-SW8
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indicates the welds were rejected by QC'due to fit up problems.
Specifically, the gap opening was. greater than 5/32 of an inch.
Proper disposition was not documented for these nonconforming
conditions in that a required nonconformance report was not prepared.
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Welds FSRR-4002-FW-2 and FSRR-4002-FW-1 were rejected by QC, however,
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the weld records indicated that the completed welds were acceptable
without having been reinspected by QC for the rejectable attribute.
This is a Severity Level IV violation.
RESPONSE
(1) Reason for the Violation
The documentation to accept the welds identified was in the packages,
however, the QC acceptance after the QC rejection was difficult to
decipher.
(2) Corrective Action That Has Been Taken
The weld packages were reviewed by a welding engineer and QC
inspectors and dispositioned acceptable as found.
(3) Corrective Action To Be Taken
LP&L procedure MM-1-054 is being revised to incorporate Weld
Specification Documentation Sheets that will allow for better
dispositioning of items in question.
(4) Date When Full Compliance Will Be Achieved
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The procedure is expected to be approved by April 15, 1987.
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