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#REDIRECT [[IR 05000382/2009201]]
{{Adams
| number = ML092320439
| issue date = 08/21/2009
| title = IR 05000382-09-201, on 03/22/2009, for Waterford, Unit 3, Security Baseline
| author name = Westreich B
| author affiliation = NRC/NSIR/DSO/DDSO
| addressee name = Kowalewski J
| addressee affiliation = Entergy Operations, Inc
| docket = 05000382
| license number = NPF-038
| contact person =
| case reference number = EA-09-139
| document report number = IR-09-201
| document type = Letter, Inspection Report
| page count = 6
}}
See also: [[see also::IR 05000382/2009201]]
 
=Text=
{{#Wiki_filter:SAFEGUARDS INFORMATIO
N    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 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
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 Commission's 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 staff's 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 NRC's 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 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
 
 
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 19:18, 11 July 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 INFORMATIO

N 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 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

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 Commission's 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 staff's 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 NRC's 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 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

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