ML20248M195
| ML20248M195 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/09/1998 |
| From: | Dyer J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Dugger C ENTERGY OPERATIONS, INC. |
| References | |
| 50-382-97-25, EA-98-310, NUDOCS 9806150134 | |
| Download: ML20248M195 (4) | |
See also: IR 05000382/1997025
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NUCLEAR REGULATORY COMMISSION
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REGION IV
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611 RYAN PLAZA DRIVE, SUITE 400
+9 * * *
June 9,1998
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EA 98-310
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Charles M. Dugger, Vice President
Operations - Waterford 3
Entergy Operations, Inc.
P.O. Box B
Killona, Louisiana 70066
SUBJECT:
RESPONSE TO NRC INSPECTION REPORT 50-382/97-25
Dear Mr. Dugger:
Thank you for your letter of April 28,1998, in response to our letter and Notice of Violation
dated March 12,1998, which identified a failure to follow procedures. We found your response
to contain all of the information required by the regulations.
In your response, you denied the Violation. We have considered your denial and the information
you presented in support of your position The results of our consideration are presented below.
We have reviewed the facts provided in your response letter and noted your position that
Waterford 3 personnel, prior to NRC identification, were not aware of the use of a 0.2 valve
factor in the Anchor-Darling evaluation of the feedwater isolation valves. Therefore, we agree
with your position that the failure to initiate a condition report did not constitute a failure to follow
your condition reporting procedure. Consequently, the Violation has been withdrawn.
However, we also noted in your response letter that you stated that the failure to perform an
adequate review of an addenda to the Anchor-Darling closure time analysis, performed in 1995
to support the installation of design change DC-3364, resulted in the use of an improper valve
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factor of 0.2 in the calculation for the closing capability of the feedwater isolation valves, and
voided a previous closure time analysis which used a 0.3 valve factor. Your letter further stated
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that you considered this to be a missed opportunity to identify the valve factor discrepancy with
these valves. The failure to adequately review this information led to L potential error in
estimating the capability of the feedwater isolation valves to perform their design basis closing
function.
Currently we understand that you are using a 0.3 valve factor to analytically predict valve
response to design basis accident conditions. This use of the 0.3 valve factor was addressed in
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the subject inspection report and identified as Unresolved item 50-382/9725-03. This valve -
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factor, did not appear to be adequately justified by the documentation that you provided to us.
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Based on a conference call on June 4,1998, between Mr. Wrape and others of your staff and
the NRC, we understand that you will perform an analytical model of the feedwater isolation
valves based on the Electric Power Research Institute (EPRI) Performance Prediction
Methodology (PPM) prior to your February 1999 refueling outLge. We also understand that any
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Entergy Operations, Inc.
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revised operability evaluations performed as a result of these activities will be provided to
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Region IV for review. In addition, we also understand that you will provide documentation
supplied by your vendor, Anchor-Darling, that supports the current use of a 0.3 valve factor for
the feedwaterisolation valves.
If our understanding is incorrect, please contact Mr. Tom Stetka of my office at (817) 860-8247.
Sincerely,
James E. Dyer
Deputy Regional Administrator
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Docket No.:
50-382
License No.: NPF-38
cc:
Executive Vice President and
Chief Operating Officer
~ Entergy Operations, Inc.
- P.O. Box 31995
Jackson, Mississippi 39286-1995
Vice President, Operations Support -
' Entergy Operations, Inc.
P.O. Box 31995
Jackson, Mississippi 39286-1995
' Wise, Carter, Child & Caraway
- P.O.' Box 651
Jackson, Mississippi 39205
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General Manager, Plant Operations
Waterford 3 SES -
l Entergy Operations, Inc.
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> P.O. Box B
- Killona' Louisiana 70066
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Entergy Operations, Inc.
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Manager- Licensing Manager
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Waterford 3 SES .
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Entergy . Operations, Inc.
P.O. Box B '
Killona, Louisiana 70066
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Chairman
Louisiana Public Service Commission
One American Place, Suite 1630
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Baton Rouge, Louisiana 70825-1697
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Director, Nuclear Safety &
Regulatory Affairs
Waterford 3 SES
. Entergy Operations, Inc.
P.O. Box B.
Killona, Louisiana . 70066
William H. Spell, Administrator
Louisiana Radiation Protection Division
P.O. Box 82135
Baton Rouge, Louisiana 70884-2135
Parish President
St. Charles Parish
P.O. Box 302
Hahnville, Louisiana 70057
Mr. William A. Cross -
Bethesda Licensing Office
3 Metro Center
Suite 610
Bethesda, Maryland 20814
Winston & Strawn
1400 L S'.reet, N.W.
Washing ton, D.C. 20005-3502
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Entergy Operations, Inc.
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Regional Administrator
Resident inspector
DRP Director
DRS-PSB
Branch Chief (DRP/D)
MIS System
Project Engineer (DRP/D)
RIV File
Branch Chief (DRP/TSS)
G. Sanborn
RIV Al 98-187 (C. Gordon)
RIV Al 98-187 (C. Goines)
OE: EA File
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DOCUMENT NAME: R:\\_WAT\\WT725ak.mfr
- previously concurred
To receive copy of document, indicate in box:"C" = Copy without enclosures "E" = Coy with endosures "N" = No copy
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OFFICIAL RECORD COPY
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