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{{#Wiki_filter:SAFEGUARDS INFORMATIO
{{#Wiki_filter:SAFEGUARDS INFORMATION
N    SAFEGUARDS INFORMATION
                                          August 21, 2009
 
EA-09-139
August 21, 2009  
Mr. Joseph Kowalewski
Vice President
Entergy Operations, Inc.
17265 River Road
EA-09-139
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


Mr. Joseph Kowalewski Vice President
                              SAFEGUARDS INFORMATION
Entergy Operations, Inc.  
J. Kowalewski                                 2
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


17265 River Road
                              SAFEGUARDS INFORMATION
Killona, LA 70057-0751
J. Kowalewski                                3
 
Because this issue involves security-related information, your response, should you
SUBJECT: PHYSICAL SECURITY BASELINE INSPECTION 05000382/2009201; PRELIMINARY GREATER THAN GREEN FINDING WATERFORD STEAM
choose to respond in writing, will not be made available electronically for public
ELECTRIC GENERATING STATION.  
inspection in the NRC Public Document Room or from the NRCs document system,
Dear Mr. Kowalewski:
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


                                        SAFEGUARDS INFORMATION
On March 22, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an on-site
      J. Kowalewski                                    3
security baseline inspection at your Waterford Steam Electric Station, Unit 3.  The inspection
      Because this issue involves security-related information, your response, should you
covered one or more of the key attributes of the security cornerstone of the NRC's Reactor Oversight Process. The enclosed inspection report documents the final inspection results, which were telephonically presented to Mr. William R. Brian, Vice President, Operations
      choose to respond in writing, will not be made available electronically for public
Support, Entergy Operations, Inc., you, and members of your staff on July 9, 2009.
      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:          SGI Custodian: TL: DSO/NSIR      BC:RIV        BC:DSO/NSIR    DD:DSO/NSIR
        DSO/NSIR              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


                              SAFEGUARDS INFORMATION
This inspection examined activities conducted under
J. Kowalewski                               3
your license as they relate to security and compliance with the Commission's rules and regulations and with the conditions of your license.  The inspectors reviewed selected procedures, records and files, observed activities, and
cc w/encl:
 
      Joseph Kowalewski, Vice President, Operations
interviewed personnel.
      Scott Anders, Security Manager, Waterford Steam Electric Generating Station
 
      D. Brady, NSIR/DSO
      J. Curry, NSIR/DSO
The attached report documents a finding that was determined to be greater than very low
      M. Shannon, RIV
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
cc w/o encl:
 
      Senior Vice President
Physical Protection Significance Determination Process (PPSDP).
          Entergy Nuclear Operations
 
      Senior Vice President and
          Chief Operating Officer
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 
          Entergy Operations, Inc.
SAFEGUARDS INFORMATION
      Vice President, Operations Support
  J. Kowalewski 2
          Entergy Services, Inc.
    SAFEGUARDS INFORMATION
      Senior Manager, Nuclear Safety
  In accordance with NRC Inspection Manual Chapter (IMC) 0609, we intend to complete
          and Licensing
our evaluation using the best available information and issue our final determination of
          Entergy Services, Inc.
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 staff's final
      Site Vice President
 
          Waterford Steam Electric Station, Unit 3
determination.
          Entergy Operations, Inc.
 
      Director
          Nuclear Safety Assurance
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
          Entergy Operations, Inc.
assess its significance, or (2) submit your position on the finding to the NRC in writing.  If
      General Manager, Plant Operations
you request a Regulatory Conference, it should be held within 30 days of the receipt of
          Waterford 3 SES
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
          Entergy Operations, Inc.
 
      Manager, Licensing
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
          Entergy Operations, Inc.
Regulatory Conference or submit a written response, you relinquish your right to appeal
      Director, Nuclear Safety & Licensing
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
          Entergy Operations, Inc.
you within 10 business days, we will continue with our significance determination and
w/o encl via e-mail:
enforcement decision and you will be advised by separate correspondence of the results of our deliberations on this matter. 
Deputy Regional Administrator (Chuck.Casto@nrc.gov)
Since the NRC has not made a final determination in this matter, no Notice of Violation is
DRP Director (Dwight.Chamberlain@nrc.gov)
being issued for these inspection findings at this time.  In addition, please be advised
DRP Deputy Director (Anton.Vegel@nrc.gov)
that the characterization of the finding described in the enclosed inspection report may
DRS Director (Roy.Caniano@nrc.gov)
change as a result of further NRC review.
DRS Deputy Director (Troy.Pruett@nrc.gov)
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 NRC's Agencywide Documents Access
Branch Chief, DRP/E (Jeff.Clark@nrc.gov)
and Management System (ADAMS), accessible from the NRC Web site at
Senior Project Engineer, DRP/E (George.Replogle@nrc.gov)
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,
WAT Site Secretary (Linda.Dufrene@nrc.gov)
as amended.  Therefore, the material will not be made available electronically for public
Public Affairs Officer (Victor.Dricks@nrc.gov)
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. 
Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov)
SAFEGUARDS INFORMATION
RITS Coordinator (Marisa.Herrera@nrc.gov)
  J. Kowalewski 3 SAFEGUARDS INFORMATION
Regional Counsel (Karla.Fuller@nrc.gov)
  Because this issue involves security-related information, your response, should you
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
choose to respond in writing, will not be made available electronically for public
OEMail Resource
inspection in the NRC Public Document Room or from the NRC's 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
DRS STA (Dale.Powers@nrc.gov)
instructions for withholding in 10 CFR 2.390(b)(1).  In accordance with 10 CFR
OEDO RIV Coordinator (Leigh.Trocine@nrc.gov)
 
ROPreports
2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
                              SAFEGUARDS INFORMATION
 
  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 NRC's 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
}}
}}

Revision as of 03:03, 14 November 2019

IR 05000382-09-201, on 03/22/2009, for Waterford, Unit 3, Security Baseline
ML092320439
Person / Time
Site: Waterford Entergy icon.png
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

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

SAFEGUARDS INFORMATION

J. Kowalewski 2

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

SAFEGUARDS INFORMATION

J. Kowalewski 3

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

SAFEGUARDS INFORMATION

J. Kowalewski 3

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: SGI Custodian: TL: DSO/NSIR BC:RIV BC:DSO/NSIR DD:DSO/NSIR

DSO/NSIR 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

SAFEGUARDS INFORMATION

J. Kowalewski 3

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

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