ML20129F526

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Forwards Insp Rept 50-382/96-20 on 960827-29 & 961003. Apparent Addl Violation Noted & Being Considered for Escalated Action.Predecisional Enforcement Conference Scheduled for 960812
ML20129F526
Person / Time
Site: Waterford Entergy icon.png
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

Text

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NUCLEAR REGULATORY COMMISSION h ,k $ REGloN IV ' + t, : - g ' S ' f* f 611 RYAN PLAZA oRIVE, SulTE 400 %,, ...../ ' ARLINGTON, T EXAS 76011 8064 I OCT 2 41996 EA 96-255 ' i 1 Michael B. Sellman, Vice President ! Operations - Waterford ' Entergy Operations, Inc.

P.O. Box B Killona, Louisiana 70066

! SUBJECT: NRC INSPECTION REPORT 50-382/96-20 ! ' 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. 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, ' , and modifies certain apparent violations identified in NRC Inspection Report 50-382/96-09. f ~ 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 , . 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. Based upon the observations and findings developed during this inspection and, after ~ 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 ' 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 2 J

_ _ _ _ _ . ______ _ _ _ - .- . _ _ _ _ _ _ g ! 't l Entergy Operations, Inc. -2- l - - - 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 enforcement action will be taken. This conference is being held to obtain information to 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 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 1 J

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i 9 Entergy Operations, Inc. -3- Should you have any questions concerning this inspection, we will be pleased to discuss them with you. Sincerely,

  1. h

nneth E.hc, han, V x ro Acting Director Division of Reactor Safety Docket No.: 50-382 License No.: NPF-38 Enclosure: NRC Inspection Report 50-382/96-20 cc w/ enclosure: 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

. . . ... - - . - . . ~ . - - . ~ . - - . - . . - . . . - . . . - .- . . . - - - - . . - - - - S ! t i f 1 l I 1 Entergy Operations, Inc. -4- . i

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Chairman Louisiana Public Service Commission i One American Place, Suite 1630 ! Baton Rouge, Louisiana 70825-1697 ( R. F. Burski, Director Nuclear Safety i Entergy Operations, Inc. l P.O. Box B l Killona, Louisiana 70066 [ l ! William H. Spell, Administrator Louisiana Radiation Protection Division ! P.O. Box 82135 Baton Rouge, Louisiana 70884-2135

i 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. l Winston & Strawn ' 1400 L Street, N.W. Washington, D.C. 20005-3502 ! !l' { . t i I . i 4 u _.

.. - - _ _ _ t . . , ' Entergy Operations, Inc. -5- E-Mail report to D. Nelson (DJN) E-Mail report to NRR Event Tracking System (IPAS) bec to DMB (IE01) . bec distrib. by RIV: L. J. Callan Resident inspector DRP Director DRS-PSB i Branch Chief (DRP/D) MIS System Project Engineer (DRP/D) RI V 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 i ) J 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% 100f/96 10/ /96 10$1/96 10#1/96 i EO D:DRP A/ AD:DRS /l/ _ j_ E anborn" JEDyer A Q phtf j4 KEBrockman 4% ff) 10/ /96 104:196 10/7f96 ' '

  • Previously concurred

' OFFICIAL RECORD COPY

[( ~ 'e 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 . i I

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 E m LEEllershaw/lW GWerner * JKudrick (l Q$lg DAPowers'd% j 100f/96 10/ /96 10$i/96 10#-l/96 EO D:DRP g AD:DRS /1/ _ j_ GSanborn* JEDyer A L pa jf /4 KEBrockman /%f/) s 10/ /96 10/gl96 10/7f96 ~

  • Previously concurred

OFFICIAL RECORD COPY ( - , }}