ML062430675

Midcycle Performance Review and Inspection Plan - Waterford 3 Steam Electric Station

ML062430675
Person / Time
Site:	Waterford
Issue date:	08/31/2006
From:	Graves D NRC/RGN-IV/DRP/RPB-E
To:	Venable J Entergy Operations
References
Download: ML062430675 (6)

Text

UNITED STATES NUCLEAR REGULATORY C 0 M M I S S I O N REGION IV 611 RYAN PLAZA DRIVE, SUITE 400 ARLINGTON, TEXAS 76011-4005 August 31,2006 Joseph E. Venable Vice President Operations Waterford 3 Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751

SUBJECT:

MIDCYCLE PERFORMANCE REVIEW AND INSPECTION PLAN -

WATERFORD 3 STEAM ELECTRIC STATION

Dear Mr. Venable:

On August 9, 2006, the NRC staff completed its performance review of Waterford 3 Steam Electric Station for the first half of the calendar year 2006 assessment cycle. Our technical staff reviewed performance indicators (PIS) for the most recent quarter and inspection results over the previous 12 months. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.

This performance review and enclosed inspection plan do not include physical protection information. A separate letter designated and marked as Official Use Only - Security-Related Information will include the physical protection review and resultant inspection plan.

Plant performance for the most recent quarter at Waterford 3 was within the Licensee Response Column of the NRCs Action Matrix, based on all inspection findings being classified as having very low safety significance (Green) and all PIS indicating performance at a level requiring no additional NRC oversight (Green). Therefore, we plan to conduct reactor oversight process (ROP) baseline inspections at your facility.

Our annual assessment letter, dated March 2, 2006, indicated our plans to conduct Inspection Procedure 71 150, Discrepant or Unreported Performance Indicator Data, in order to resolve a potential discrepancy related to reporting safety system unavailability PI data for Train B of the emergency core cooling system. NRC conducted this inspection and the results are documented in NRC Inspection Report 05000382/2006009 dated August 30, 2006. This inspection concluded that the data regarding fault exposure hours for the High Pressure Safety Injection System, Train B, and the Containment Spray System, Train B, had been reported incorrectly. If the data had been reported accurately (Le., with the correct use of fault exposure hours) in late 2004, when initially identified, then the safety system unavailability PIS regarding the two addressed systems would have changed color from Green to Red and Green to Yellow, respectively. Even though the actual risk of the underlying performance deficiency was determined to be Green, as documented in NRC Inspection Report 05000382/2004005, plant performance would have been assessed in the Multiple/Repetitive Degraded Cornerstone column of NRCs Action Matrix.

Entergy Operations, Inc. The safety system unavailability PISwere replaced with the Mitigating System Performance Index beginning April 1, 2006, as addressed in Regulatory Issue Summary 2006-07, Changes to the Safety System Unavailability Performance Indicators, dated June 12, 2006. Because the inaccurately reported data would have had no significant impact on the Mitigating Systems Performance Index indicators (which were Green for the most recent quarter), and most important, the very low risk significance associated with the performance deficiency that resulted in the initial fault exposure time, the NRC determined that the demonstrated level of performance is more indicative of the Licensee Response column rather than the Multiple/Repetitive Degraded Cornerstone column. Consequently, the NRC approved a deviation from the NRC Action Matrix that authorized taking action in accordance with the Licensee Response column of NRCs Action Matrix. As documented in NRC Inspection Report 05000382/2006009, dated August 30, 2006, enforcement action was also taken for reporting inaccurate performance indicator data.

The enclosed inspection plan details the inspections, including Temporary Instructions, except those related to physical protection, scheduled through March 31 , 2008. The inspection plan is provided to minimize the resource impact on your staff and to allow for the early resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature.

The inspections in the last 9 months of the inspection plan are tentative and may be revised at the annual performance assessment review meeting.

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.nov/reading-rm/adams. html (the Public Electronic Reading Room).

If circumstances arise which cause us to change the inspection plan, we will contact you to discuss the change as soon as possible. Please contact me at (817) 860-8147 with any questions you may have regarding this letter or the inspection plan.

Sincere1y ,

David N. Graves, Chief Project Branch E Division of Reactor Projects Docket: 50-382 License: NPF-38

Enclosure:

Waterford 3 Steam Electric Station Inspection/Activity Plan

Entergy Operations, Inc. cc w/enclosure:

Senior Vice President and Parish President Chief Operating Officer St. Charles Parish Entergy Operations, Inc. P.O. Box 302 P.O. Box 31995 Hahnville, LA 70057 Jackson, MS 39286-1995 Winston & Strawn LLP Vice President, Operations Support 1700 K Street, N.W.

Entergy Operations, Inc. Washington, DC 20006-3817 P.O. Box 31995 Jackson, MS 39286-1995 Institute of Nuclear Power Operations (INPO)

Records Center Wise, Carter, Child & Caraway 700 Galleria Parkway SEI Suite 100 P.O. Box 651 Atlanta, GA 30339 Jackson, MS 39205 General Manager, Plant Operations Waterford 3 SES Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751 Manager - Licensing Manager Waterford 3 SES Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751 Chairman Louisiana Public Service Commission P.O. Box 91 154 Baton Rouge, LA 70821-9154 Director, Nuclear Safety &

Regulatory Affairs Waterford 3 SES Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751 Richard Penrod, Senior Environmental Scientist Office of Environmental Services Northwestern State University Russsell Hall, Room 201 Natchitoches, LA 71497

Entergy Operations, Inc. Electronic distribution by RIV:

Regional Administrator (BSMI)

DRP Director (ATH)

DRS Director (DDC)

DRS Deputy Director (RJCI)

Senior Resident Inspector (GFLI)

Branch Chief, DRP/E (DNG)

Senior Project Engineer, DRP/E (VGG)

Team Leader, DRP/TSS (RLNI)

RlTS Coordinator (KEG)

V. Dricks, P A 0 (VLD)

W. Maier, RSLO (WAM)

C. Gordon (CJG)

DRS Branch Chiefs (JAC, ATG, LJS, MPSI)

B. Wetzel, Chief, TRPS, OED0 (BAW)

S. Richards, Deputy Director, DIRS, NRR (SAR)

C. Holden, Deputy Director, DORL, NRR (CFH)

C. Haney, Director, DORL, NRR (CXH)

D. Terao, Chief, LPLG, DORL, NRR (DXT)

M. Fields, NRR Project Manager for Waterford (MBFI)

SUNS1 Review Completed: -DNG- ADAMS: {Yes 0 No Initials: -DNG J Publicly Available 0 Non-Publicly Available 0 Sensitive J Non-Sensitive R:\ REACTORS\EOC and Midcvcle\Midcvcle Assessment Letters\2006\WT.w~d I RIV:C/DRP/E ID:DRS I D:DRP 11 DNGraves OFFICIAL RECORD COPY 6 F T eIe hone E=E-mail F=Fax

m m IC c - m N r r r m N

W-gr.4 O O N m m m m m m m m m m m m m m m m m m m m m m m m a 0 as n o =

E

c o rC C n rn r n r n C (0

C 0 C 0 C 0

.P c

.P c

.-c .-

c c

.-0 L

o o o o o ala, a, m Q a Q, a, Q

a n Q

-cr n r-cn m a ,

- rn C

-crm na-cw, -C

.E .E -.-C a,

- -.E

.r a,

-a, 2m % m s sm sm m m 2 m m 2 b b 0b b b b b b b 0 b b b b 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 c!c!

$ $ s.

0 g $

N -

c!c!c!

sss c!c!c!

$ $ E . 2...

N 0

b -

2 2 7 -

c!c!c!

z...z z s0 i 0 a m 0 G 0 0 Z 0 0 0 z z z 0 0 0 m

0 2 2 2 2 2 2 b

0 0

b 0

0 b

0 b

0 0

b 0

0 b

0 0

b 0

0 b

0 0

b 0

0 b

0 0

0 0

0 0

Yc! c! 9 9 g g g Q P c ! c!

2:

g @ %

m 0

$ E 0 0 3 .

2:s 0 0 0

$ $ $ 1 z z z 0 0 0 m

s 0

LD - r - r  %- m m r I

m C

m

• m m rn m rn 6

!2  !?!

6 5 2 c

m C

rn I

C a,

c 0

i8E m

C C

a,

.-C c

2 m 0 0 o 0 0 N

0 7

2 7

II: