ML20129F526
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| ML20129F526 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/24/1996 |
| From: | Brockman K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Sellman M ENTERGY OPERATIONS, INC. |
| Shared Package | |
| ML20129F533 | List: |
| References | |
| NUDOCS 9610290153 | |
| Download: ML20129F526 (5) | |
See also: IR 05000382/1996020
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OCT 2 41996
EA 96-255 '
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Michael B. Sellman, Vice President !
Operations - Waterford '
Entergy Operations, Inc. ;
P.O. Box B
Killona, Louisiana 70066 :
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SUBJECT: NRC INSPECTION REPORT 50-382/96-20 !
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Dear Mr. Sellman:
From August 27-29,1996, an NRC inspection was conducted at your Waterford Steam
Electric Station, Unit 3, reactor facility, with in-office inspection and followup conducted ,
through October 3,1996. This inspection was conducted to further review information
related to issues identified in NRC Inspection Report 50-382/96-09, dated July 24,1996.
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A telephonic exit meeting was conducted on October 9,1996, with you and members of ,
your staff. The enclosed report presents the scope and results of the current inspection,
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and modifies certain apparent violations identified in NRC Inspection Report 50-382/96-09. I
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Previously, NRC Inspection Report 50-382/96-09 identified three apparent violations: (1)
, an apparent violation of Criterion XVI of Appendix B to 10 CFR Part 50 regarding a f ailure , to promptly correct identified deficiencies in the inservice test program (IST); (2) an
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apparent violation of 10 CFR 50.55a and the ASME Code regarding a failure to include
! required valves in the IST plan; and, (3) an apparent violation of Technical Specification
- 4.0.5 regarding the failure to perform required testing on safety-related valves in the IST
plan. These apparent violations were being considered for escalated action in accordance
, with the " General Statement of Policy and Procedure for NRC Enforcement Actions" 1 (Enforcement Policy), NUREG-1600. A predecisional enforcement conference had been j scheduled for August 12,1996. However, your staff's follow-up to an unresolved item
listed in the inspection report identified that the containment vacuum relief system may not
have been built in accordance with the Final Safety Analysis Report (reference your
Licensee Event Report 50-382/96-009, dated August 26,1996). Because of concerns we
had related to this issue, the predecisional enforcement conference was postponed and this
current inspection was conducted.
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Based upon the observations and findings developed during this inspection and, after
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reviewing the concerns detailed in NRC Inspection Report 50-382/96-09,we have
determined that the issues related to the apparent violations of 10 CFR 50.55a and
Technical Specification 4.0.5, are subsumed in the apparent violation of Criterion XVI of l
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Appendix B to 10 CFR Part 50. Therefore, we are identifying one apparent violation from
that inspection report, specifically that related to the Criterion XVI of Appendix B to
9610290153 961024 "*
gDR ADOCK 05000382
PDR
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Entergy Operations, Inc. -2-
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10 CFR Part 50. Even though the number of apparent violations has been reduced, we
expect your staff to fully discuss the circumstances related to all of these issues. This will
allow the NRC to verify that these issues are appropriately encompassed within a single
violation.
This inspection also identified two additional apparent violations which are being
considered for escalated action in accordance with NRC's Enforcement Policy. These 1
relate to: (1) a failure to close a containment spray valve following completion of pump
testing; and (2) a failure to perform the required written safety evaluation to provide the
bases for a determination that the difference between the facility design configuration and
the Final Safety Analysis Report did not involve an unreviewed safety question. These
three apparent violations incorporate all enforcement issues identified between the two
NRC inspection reports; accordingly, no Notice of Violation is presently being issued for
these inspection findings. In addition, please be advised that the number and
characterization of apparent violations described in the enclosed inspection report may
change as a result of further NRC review.
A predecisional enforcement conference to discuss these apparent violations will be i
scheduled with your staff. The decision to hold a predecisional enforcement conference )
does not mean that the NRC has determined that a violation has occurred or that l
enforcement action will be taken. This conference is being held to obtain information to l
enable the NRC to make an enforcement decision, such as a common understanding of the j
facts, root causes, missed opportunities to identify the apparent violations sooner, !
corrective actions, significance of the issues and the need for lasting and effective
corrective action. We are also interested in your perspective regarding the risk significance
of the f ailure to close containment spray Valve CS 118A. In addition, this is an !
opportunity for you to point out any errors in our inspection reports and for you to provide
any information concerning your perspectives on 1) the severity of the violations,2) the
application of the factors that the NRC considers when it determines the amount of a civil l
penalty that may be assessed in accordance with Section VI.B.2 of the Enforcement Policy, l
and 3) any other application of the Enforcement Policy to this case, including the exercise
of discretion in accordance with Section Vll.
You will be advised by separate correspondence of the results of our deliberations on this
matter. No response regarding these apparent violations is required at this time.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter
and its enclosure will be placed in the NRC Public Document Room (PDR). i
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Entergy Operations, Inc. -3-
Should you have any questions concerning this inspection, we will be pleased to discuss
them with you.
Sincerely,
x
nneth E.hc,ro
#h han, VDirector
Acting
Division of Reactor Safety
Docket No.: 50-382
License No.: NPF-38
Enclosure:
NRC Inspection Report
50-382/96-20
cc w/ enclosure:
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Harry W. Keiser, Executive Vice
President and Chief Operating Officer
Entergy Operations, Inc.
P.O. Box 31995
Jackson, Mississippi 39286-1995
Jerrold G. Dewease, Vice President
Operations Support
Entergy Operations, Inc.
P.O. Box 31995
Jackson, Mississippi 39286-1995
Robert B. McGehee, Esq.
Wise, Carter, Child & Caraway
P.O. Box 651
Jackson, Mississippi 39205
D. R. Keuter, General Manager
Plant Operations
Entergy Operations, Inc.
P.O. Box B
Killona, Louisiana 70066
Donald W. Vinci, Licensing Manager
Entergy Operations, Inc.
P.O. Box B
Killona, Louisiana 70066
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Entergy Operations, Inc. -4- .
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Chairman !
Louisiana Public Service Commission i
One American Place, Suite 1630 !
Baton Rouge, Louisiana 70825-1697
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R. F. Burski, Director Nuclear Safety i
Entergy Operations, Inc. l
P.O. Box B l
Killona, Louisiana 70066
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William H. Spell, Administrator
Louisiana Radiation Protection Division
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P.O. Box 82135
Baton Rouge, Louisiana 70884-2135 ;
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Parish President
St. Charles Parish' ]'
l P.O. Box 302
Hahnville, Louisiana 70057
Mr. William A. Cross
Bethesda Licensing Office
3 Metro Center
Suite 610
Bethesda, Maryland 20814
Nicholas S. Reynolds, Esq.
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Winston & Strawn
1400 L Street, N.W.
Washington, D.C. 20005-3502
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E-Mail report to D. Nelson (DJN)
E-Mail report to NRR Event Tracking System (IPAS)
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bec distrib. by RIV:
L. J. Callan Resident inspector l
DRP Director DRS-PSB i
Branch Chief (DRP/D) MIS System l
Project Engineer (DRP/D) RI V File
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Branch Chief (DRP/TSS)
Leah Tremper (OC/LFDCB, MS: TWFN 9E10)
G. F. Sanborn, EO ;
W. L. Brown, RC
OE:EA File, MS: 7-H-5
J. Lieberman, OE, MS: 7-H-5
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DOCUMENT NAME: R:\_WAT\_WT620rp. lee
To receive copy of doqument. Indicate in box: "C" = Copy without enclosures 7" = Copy with enclosures "N" = No copy
RIV:RI:MB & E PE:PBD ME:NRR R 5 C:MB , E
LEEllershaw/lW GWerner * JKudrick T( Q$.X DAPowers'd%
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10/ /96 104:196 10/7f96
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*Previously concurred
OFFICIAL RECORD COPY
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Entergy Operations, Inc. -5- ,
E-Mail report to D. Nelson (DJN)
E-Mail report to NRR Event Tracking System (IPAS)
%II8UEB'(iEU'1TI"'[[*
bec distrib. by RIV:
L. J. Callan Resident inspector :
DRP Director DRS-PSB
Branch Chief (DRP/D) MIS System
Project Engineer (DRP/D) RIV File
Branch Chief (DRP/TSS)
Leah Tremper (OC/LFDCB, MS: TWFN 9E10)
G. F. Sanborn, EO
W. L. Brown, RC ,
OE:EA File, MS: 7-H-5 '
J. Lieberman, OE, MS: 7-H-5 .
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DOCUMENT NAME: R:\_WAT\_WT620rp. lee l
To receive copy of Mument. Indicate in box: "C" = Copy without enclosures K" = Copy with enclosures *N" = No copy
RIV:RI:MB Ql E PE:PBD l ME:NRR M M C:MB m E
LEEllershaw/lW GWerner * JKudrick (l Q$lg DAPowers'd% j
100f/96 10/ /96 10$i/96 10#-l/96
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GSanborn* JEDyer A L pa s jf /4 KEBrockman /%f/) l
10/ /96
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10/gl96 10/7f96 l
* Previously concurred
OFFICIAL RECORD COPY
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