ML092320439

IR 05000382-09-201, on 03/22/2009, for Waterford, Unit 3, Security Baseline

ML092320439
Person / Time
Site:	Waterford
Issue date:	08/21/2009
From:	Westreich B NRC/NSIR/DSO/DDSO
To:	Kowalewski J Entergy Operations
References
EA-09-139 IR-09-201
Download: ML092320439 (6)

See also: IR 05000382/2009201

Text

SAFEGUARDS INFORMATION

SAFEGUARDS INFORMATION

August 21, 2009

EA-09-139

Mr. Joseph Kowalewski

Vice President

Entergy Operations, Inc.

17265 River Road

Killona, LA 70057-0751

SUBJECT:

PHYSICAL SECURITY BASELINE INSPECTION 05000382/2009201;

PRELIMINARY GREATER THAN GREEN FINDING WATERFORD STEAM

ELECTRIC GENERATING STATION.

Dear Mr. Kowalewski:

On March 22, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an on-site

security baseline inspection at your Waterford Steam Electric Station, Unit 3. The inspection

covered one or more of the key attributes of the security cornerstone of the NRCs Reactor

Oversight Process. The enclosed inspection report documents the final inspection results,

which were telephonically presented to Mr. William R. Brian, Vice President, Operations

Support, Entergy Operations, Inc., you, and members of your staff on July 9, 2009.

This inspection examined activities conducted under your license as they relate to security and

compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures, records and files, observed activities, and

interviewed personnel.

The attached report documents a finding that was determined to be greater than very low

security significance (i.e., greater than Green as determined by the Physical Protection

Significance Determination Process). The finding is described in Section 3.26 of the enclosed

inspection report. This finding was assessed based on the best available information, using the

Physical Protection Significance Determination Process (PPSDP).

The deficiencies were corrected or compensated for, and the plant was in compliance with

applicable physical protection and security requirements within the scope of this inspection

before the inspectors left the area.

Enclosure contains Safeguards Information. Upon Removal, this letter is decontrolled

SAFEGUARDS INFORMATION

J. Kowalewski

2

SAFEGUARDS INFORMATION

In accordance with NRC Inspection Manual Chapter (IMC) 0609, we intend to complete

our evaluation using the best available information and issue our final determination of

safety significance within 90 days of the date of this letter. The significance

determination process (SDP) encourages an open dialogue between the NRC staff and

the licensee; however, the dialogue should not impact the timeliness of the staffs final

determination.

Before we make our final significance determination, we are providing you with an

opportunity (1) to attend a Regulatory Conference where you can present to the NRC

your perspective on the facts and assumptions the NRC used to arrive at the finding and

assess its significance, or (2) submit your position on the finding to the NRC in writing. If

you request a Regulatory Conference, it should be held within 30 days of the receipt of

this letter and we encourage you to submit supporting documentation at least one week

prior to the conference in an effort to make the conference more efficient and effective.

If a Regulatory Conference is held, it will not be open for public observation. If you

decide to submit only a written response, such submittal should be sent to the NRC

within 30 days of your receipt of this letter.

In the interest of protecting sensitive, security-related information, if a Regulatory

Conference is held, it will not be open for public observation. If you decline to request a

Regulatory Conference or submit a written response, you relinquish your right to appeal

the final significance determination, in that by not doing either, you fail to meet the

appeal requirements stated in the Prerequisite and Limitation sections of Attachment 2

of IMC 0609.

Please contact Robert C. Johnson at (301) 415-6640 within 10 business days from the

issue date of this letter to notify the NRC of your intentions. If we have not heard from

you within 10 business days, we will continue with our significance determination and

enforcement decision and you will be advised by separate correspondence of the results

of our deliberations on this matter.

Since the NRC has not made a final determination in this matter, no Notice of Violation is

being issued for these inspection findings at this time. In addition, please be advised

that the characterization of the finding described in the enclosed inspection report may

change as a result of further NRC review.

In accordance with 10 Code of Federal Regulations (CFR) 2.390 of the NRC's "Rules of

Practice," a copy of this letter will be made available electronically for public inspection in

the NRC Public Document Room or from the NRCs Agencywide Documents Access

and Management System (ADAMS), accessible from the NRC Web site at

http://www.nrc.gov/reading-rm/adams.html. The material enclosed herewith contains

Safeguards Information (SGI) as defined by 10 CFR Part 73.21 and its disclosure to

unauthorized individuals is prohibited by Section 147 of the Atomic Energy Act of 1954,

as amended. Therefore, the material will not be made available electronically for public

inspection in the NRC Public Document Room or from ADAMS, accessible from the

NRC Web site at http://www.nrc.gov/reading-rm/adams.html.

SAFEGUARDS INFORMATION

J. Kowalewski

3

SAFEGUARDS INFORMATION

Because this issue involves security-related information, your response, should you

choose to respond in writing, will not be made available electronically for public

inspection in the NRC Public Document Room or from the NRCs document system,

ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-

rm/adams.html. If SGI is necessary to provide an acceptable response, please provide

the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response

Proprietary Information in accordance with 10 CFR 2.390(d)(1) and follow the

instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR

2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.

Sincerely,

/RA/

Barry C. Westreich, Deputy Director

Division of Security Operations

Office of Nuclear Security and Incident Response

SAFEGUARDS INFORMATION

J. Kowalewski

3

SAFEGUARDS INFORMATION

Because this issue involves security-related information, your response, should you

choose to respond in writing, will not be made available electronically for public

inspection in the NRC Public Document Room or from the NRCs document system,

ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-

rm/adams.html. If SGI is necessary to provide an acceptable response, please provide

the level of protection described in 10 CFR 73.21. Otherwise, mark your entire response

Proprietary Information in accordance with 10 CFR 2.390(d)(1) and follow the

instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR

2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.

Sincerely,

/RA/

Barry C. Westreich, Deputy Director

Division of Security Operations

Office of Nuclear Security and Incident Response

Docket No.:

50-382

License No.: NPF-38

Enclosure(s): Inspection Report No. 05000382/2009201 (SGI)

Distribution w/encl:

SPEB R/F -

M. Shannon, R-IV

D. Overland, SRI, Waterford

Distribution w/o encl:

N. Kalyanam, PM - NRR

T. Howard, PMDA

Accession No. ML

OFFICE

Originator:

DSO/NSIR

SGI Custodian:

DSO/NSIR

TL: DSO/NSIR

BC:RIV

BC:DSO/NSIR

DD:DSO/NSIR

NAME

ALetourneau

JCurry

RFelts

MShannon

RJohnson

BWestreich

DATE

08/ /2009

08/ /2009

08/ /2009

08/ /2009

08/ /2009

08/21/2009

Official Record Copy

SAFEGUARDS INFORMATION

J. Kowalewski

3

SAFEGUARDS INFORMATION

cc w/encl:

Joseph Kowalewski, Vice President, Operations

Scott Anders, Security Manager, Waterford Steam Electric Generating Station

D. Brady, NSIR/DSO

J. Curry, NSIR/DSO

M. Shannon, RIV

cc w/o encl:

Senior Vice President

Entergy Nuclear Operations

Senior Vice President and

Chief Operating Officer

Entergy Operations, Inc.

Vice President, Operations Support

Entergy Services, Inc.

Senior Manager, Nuclear Safety

and Licensing

Entergy Services, Inc.

Site Vice President

Waterford Steam Electric Station, Unit 3

Entergy Operations, Inc.

Director

Nuclear Safety Assurance

Entergy Operations, Inc.

General Manager, Plant Operations

Waterford 3 SES

Entergy Operations, Inc.

Manager, Licensing

Entergy Operations, Inc.

Director, Nuclear Safety & Licensing

Entergy Operations, Inc.

w/o encl via e-mail:

Deputy Regional Administrator (Chuck.Casto@nrc.gov)

DRP Director (Dwight.Chamberlain@nrc.gov)

DRP Deputy Director (Anton.Vegel@nrc.gov)

DRS Director (Roy.Caniano@nrc.gov)

DRS Deputy Director (Troy.Pruett@nrc.gov)

Branch Chief, DRP/E (Jeff.Clark@nrc.gov)

Senior Project Engineer, DRP/E (George.Replogle@nrc.gov)

WAT Site Secretary (Linda.Dufrene@nrc.gov)

Public Affairs Officer (Victor.Dricks@nrc.gov)

Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

Regional Counsel (Karla.Fuller@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov)

OEMail Resource

DRS STA (Dale.Powers@nrc.gov)

OEDO RIV Coordinator (Leigh.Trocine@nrc.gov)

ROPreports