INFORMATION REPORT

June 4, 2007 SECY-07-0087

For: The Commissioners

From: Vonna L. Ordaz, Assistant for Operations, Office of the EDO

Subject: WEEKLY INFORMATION REPORT - WEEK ENDING

MAY 11, 2007

Contents Enclosure

Nuclear Reactor Regulation A

New Reactors B*

Nuclear Material Safety and Safeguards C

Federal and State Materials and Environmental Management Programs D*

Nuclear Regulatory Research E

Nuclear Security and Incident Response F

Administration G

Information Services H

Chief Financial Officer I*

Human Resources J

Small Business and Civil Rights K*

Enforcement L*

Public Affairs M

International Programs N*

Secretary O

Region I P*

Region II P* 

Region III P*

Region IV P

Executive Director for Operations Q*

Congressional Affairs R

*No input this week.

/RA/

Vonna L. Ordaz 

Assistant for Operations, OEDO

Contact:

U. Shoop, OEDO
June 4, 2007 SECY-07-0087

For: The Commissioners

From: Vonna L. Ordaz, Assistant for Operations, Office of the EDO

Subject: WEEKLY INFORMATION REPORT - WEEK ENDING

MAY 11, 2007

Contents Enclosure

Nuclear Reactor Regulation A

New Reactors B*

Nuclear Material Safety and Safeguards C

Federal and State Materials and Environmental Management Programs D*

Nuclear Regulatory Research E

Nuclear Security and Incident Response F

Administration G

Information Services H

Chief Financial Officer I*

Human Resources J

Small Business and Civil Rights K*

Enforcement L*

Public Affairs M

International Programs N*

Secretary O

Region I P*

Region II P*

Region III P*

Region IV P

Executive Director for Operations Q*

Congressional Affairs R

*No input this week.

/RA/

Vonna L. Ordaz

Assistant for Operations, OEDO

Contact:

U. Shoop, OEDO

DISTRIBUTION:

EDO R/F

AO R/F Document Name: C:\WIR\week511.WPD

OEDO ljr for AO/OEDO

UShoop:paa VLOrdaz

06/04/07 06/04/07
WEEKLY INFORMATION REPORT - WEEK ENDING MAY 11, 2007

The Weekly Information Report is compiled by the Office of the EDO and includes highlights of

Headquarters and Regional Office activities. 

Contact: U. Shoop, OEDO by E-mail: USS@nrc.gov. 

Use GO TO (Ctrl+Home) to advance to the page number for a specific Office.

PgDn and PgUp can also be used to advance through the text.

OFFICE Page OFFICE Page

NRR 2 OE *

NRO * OPA 17

NMSS 4 OIP *

FSME * SECY 19

RES 9 Region I *

NSIR 10 Region II *

ADM 11 Region III *

OIS 12 Region IV 23

CFO * EDO *

HR 16 OCA 24

SBCR *

*No input this week
May 11, 2007 ENCLOSURE A

Office of Nuclear Reactor Regulation (NRR)

Items of Interest

Week Ending May 11, 2007

Regulatory Information Exchange Meeting with Swiss Regulatory Authority, HSK

During May 2-4, 2007, staff from NRR, Office of Nuclear Regulatory Research (RES) and

Office of New Reactors (NRO) conducted a series of information exchange meetings with

Dr. Ulrich Schmocker, head of the Swiss Nuclear Regulatory authority (HSK) and his senior

staff. The topics discussed included: evaluation of seismic hazards in safety assessment;

applications of probabilistic safety assessment including risk informed regulation; licensing of

new reactors; ageing and materials degradation; and license renewal. In addition, Dr.

Schmocker presented the HSK Integrated Management System (HSKIMS) and his experience

in using the system over the past 7 years. 

Meeting with Electric Power Research Institute Regarding Steam Generator Issues

During May 2 - 3, 2007, staff participated in a public meeting with representatives of Nuclear

Energy Institute and the Electric Power Research Institute (EPRI) at EPRI facilities in Charlotte,

NC. The topics covered during this meeting included steam generator (SG) tube inspection

sampling plans for satisfying technical specification requirements, tools for assessing SG tube

integrity, process for qualifying SG tube inspection techniques, and a number of SG technical

issues (e.g., impact of operating leakage on the amount of accident induced leakage, divider

plate weld cracking, etc). In addition to the formal discussions, EPRI provided a tour of their

non-destructive evaluation and performance demonstration laboratories. The staff will continue

interactions with the industry on SG technical issues.

Meeting with Michigan Power Company Regarding Generic Safety Issue (GSI)-191,

“Assessment of Debris Accumulation on PWR Sump Performance”

On May 8, 2007, staff participated in a public meeting with representatives of Indiana Michigan

Power Company regarding current activities to address Generic Letter 2004-02, “Potential

Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at

Pressurized-Water Reactors,” at D.C. Cook. The licensee representatives described their

actions to date as well as their proposed strategy to resolve outstanding technical issues such

as chemical effects and downstream effects. The staff provided feedback on various technical

aspects of the proposed strategy for issue resolution.

Meeting with the Industry on Pressurizer Dissimilar Metal Welds Advanced Fracture Mechanics

Analyses

On May 8, 2007, staff from NRR and RES, along with a RES contractor, met with

representatives of EPRI, Dominion Engineering (EPRI’s contractor), and members of EPRI’s

expert panel. This meeting was held to discuss industry’s advanced fracture mechanics

program which is being undertaken to address concerns with the potential for significant

primary water stress corrosion cracking in pressurizer dissimilar metal nozzle butt welds. The

meeting participants discussed the industry’s progress to date, responses to technical concerns

provided in the staff’s April 4, 2007, letter to the Nuclear Energy Institute, and the industry’s
May 11, 2007 ENCLOSURE A

proposed sensitivity study matrix of analysis cases. The industry provided responses to all the

technical concerns in the April 4, letter and the staff will evaluate the industry’s response. 

Reactor Oversight Process (ROP) Public Meeting on Seabrook License Appeal

On May, 9, 2007, staff conducted a public meeting on a ROP performance indicator Frequently

Asked Question (FAQ), related to the licensee’s appeal of FAQ 67.3 for the emergency diesel

generator “B” high jacket water temperature at Seabrook.

Davis-Besse Nuclear Power Station - 10 CFR 2.206 Petition

By letter dated April 30, 2007, the Union of Concerned Scientists submitted a 10 CFR 2.206

petition request to the NRC concerning a recently-docketed technical report prepared by the

licensee’s consultants in support of an insurance claim related to Davis-Besse’s 2002 reactor

vessel head corrosion. The petition requested the NRC (1) to immediately order the shutdown

of Davis-Besse, (2) to shutdown of all pressurized water reactors in the United States if the

report was subsequently validated by the NRC, and (3) to revoke Davis-Besse’s operating

license if the NRC determines that inaccurate information was submitted by the licensee.

On May 3, 2007, the NRC’s petition review board (PRB) informed the petitioner by telephone

that the request to immediately shut down Davis-Besse was denied because the NRC did not

believe that an immediate safety concern existed. The NRC staff further informed the petitioner

that the PRB had not yet made an initial assessment on the two other items in the petition

request. The PRB will meet on May 9, 2007, to address the remaining requests of the petition.

Operator Licensing Examinations at Reed College

During the weeks of April 29 and May 6, 2007, staff conducted operator licensing examinations

at Reed College in Portland Oregon. The staff administered examinations to more than twenty

applicants applying for licenses to operate the school’s 250 Kilowatt TRIGA® reactor. The

twenty applicants represent approximately twenty percent of the operator licensing

examinations to be administered at research and test reactors for the fiscal year.
May 11, 2007 ENCLOSURE C

Office of Nuclear Material Safety and Safeguards (NMSS)

Items of Interest

Week Ending May 11, 2007

Issuance of “RIS 2007-09, Examples of Recurring Requests for Additional Information (RAIs)

for 10 CFR Part 71 and Part 72 Applications”

During a meeting with industry representatives at the Licensing Process Conference in

February 2005, the point was made that it might be possible to reduce the number of recurring

Requests for Additional Information (RAIs) questions, asked in conjunction with a licensing

action, if the staff could identify, and send out to licensees, a list of examples of RAIs that NRC

repeatedly has had to address for multiple applicants.

On May 4, 2007, the staff issued “RIS 2007-09, Examples of Recurring Requests for Additional

Information (RAIs) for 10 CFR Part 71 and Part 72 Applications.” This Regulatory Information

Summary is being issued to inform addressees of RAI questions that have been asked

repeatedly when reviewing applications and amendments under Parts 71 and 72, so as to

illustrate technical areas in which applicants may be able to address issues before submitting

applications for NRC review. This list of questions is not exhaustive and does not limit the

scope of questions that may be asked by NRC staff, but rather is intended as a guide for

applicants to use in an attempt to reduce or eliminate potential RAI questions.
May 11, 2007 ENCLOSURE E

Office of Nuclear Regulatory Research (RES)

Items of Interest

Week Ending May 11, 2007

Meeting with Canadian Nuclear Safety Commission on Digital Instrumentation and Control

(I&C) Risk Analysis

On May 9, 2007, staff met with a representative of the Canadian Nuclear Safety Commission

(CNSC) to discuss NRC and CNSC work on reliability modeling of digital systems. The NRC

participants provided a briefing on the ongoing RES work on both traditional and dynamic

methods for modeling and quantifying digital system reliability. The CNSC participant provided

information on planned digital I&C risk research activities at CNSC, which will initially focus on

the area of fault coverage.

Implementing Agreement with the Health and Safety Executive of Great Britain to Participate in

the NRC’s Cooperative Severe Accident Research Program (CSARP)

On May 8, 2007, the NRC’s Executive Director for Operations signed the subject agreement.

The CSARP work expands the NRC's and the international community's data and knowledge

base in the area of severe accident research and provides insights on severe accident

computer code development, assessment, and applications. The NRC uses the MELCOR code

to evaluate potential severe-accident scenarios, to address regulatory and licensing issues for

operating plants, and to review new designs. This Implementing Agreement includes Great

Britain in the international MELCOR user community. The severe accident work performed, the

technical information exchanged, and the code assessments and feedback provided help

provide quality assurance of NRC's reactor safety codes. The next step is for the signed

Implementing Agreement to be sent to Great Britain for countersignature. This Implementing

Agreement will become effective upon signature and will remain in effect for a period of five

years.
May 11, 2007 ENCLOSURE F

Office of Nuclear Security and Incident Response (NSIR)

Items of Interest

Week Ending May 11, 2007

Preliminary Notifications

1. PNO-II-07-004A, VOGTLE NUCLEAR PLANT, AUTOMATIC REACTOR TRIP/PLANT

SHUTDOWN GREATER THAN 72 HOURS - UPDATED.

2. PNO-III-07-006, PALISADES NUCLEAR PLANT, PALISADES SHUTDOWN DUE TO

LOW STEAM GENERATOR LEVEL.
May 11, 2007 ENCLOSURE G

Office of Administration (ADM)

Items of Interest 

Week Ending May 11, 2007

List of Approved Spent Fuel Storage Casks: NAC–MPC Revision 5 (AI13 - Part 72)

On May 10, 2007, the NRC published a direct final rule in the Federal Register (72 FR 26535)

that amends the entry for the NAC International, Inc., NAC-Multi-Purpose Canister (MPC) cask

system in the list of approved spent fuel storage casks (Amendment 5). This action modifies

the Certificate of Compliance (CoC) by revising the Technical Specifications (TS) to incorporate

changes to the reporting and monitoring requirements to allow for visual inspection of the air

inlet and outlet vents instead of thermal monitoring, and to replace all references to backfilling

the cask with air to backfilling with inert gas. The rule also revises the CoC description to

remove the requirement for tamper-indicating devices on the Vertical Concrete Casks. The

direct final rule becomes effective July 24, 2007.

On May 10, 2007, the NRC published the companion proposed rule to this direct final rule in the

Federal Register (72 FR 26568). The comment period closes June 11, 2007.

Contract Awarded to Interpark Holdings, Inc.

On May 8, 2007, a contract (NRC-10-07-449) was awarded to Interpark Holdings, Inc. This

procurement provides for 22 parking spaces at the Bethesda Gateway facility. The period of

performance is June 1, 2007 through May 31, 2008 and four 1-year option periods. The total

amount of the award is $92,400 (NRC’s portion). 
May 11, 2007 ENCLOSURE H

Office of Information Services (OIS)

Items of Interest

Week Ending May 11, 2007

Freedom of Information Act (FOIA) and Privacy Act Requests Received During the Period of

May 4 through May 10, 2007:

Access authorization, any and all documents, records and reports

that form the basis of eligibility, including 3-19-07 memo from the

Director, DFS to the DEDO, re: access authorization and entire

investigation file

FOIA/PA-2007-0194

Companies/businesses with current radioactive material

licenses/permits within specified cities within 25 miles of Dover AFB,

Kent County, Delaware; provide specific isotope and maximum

activity authorized for each item

FOIA/PA-2007-0195

Companies/businesses with current radioactive material

licenses/permits within specified cities within 25 miles of Fairchild

AFB, Spokane County, Washington; provide specific isotope and

maximum activity authorized for each item

FOIA/PA-2007-0196

TWA Airlines LLC site located at 9200 NW 112 Street, Kansas City,

MO, status and information

FOIA/PA-2007-0197

Radiation leak (including Cobalt 60 and 58) detected at Yokosuka

Port in Japan in September 2006 while USS Honolulu was visiting, all

records

FOIA/PA-2007-0198

OI investigation file 3-2005-010, entire file and all exhibits, supporting

documentation including transcripts

FOIA/PA-2007-0199

RIII-04-A-0143 including Allegation Board actions, all records relevant

and/or related to concerns raised by named individual

FOIA/PA-2007-0200

National Enrichment Facility Safety Analysis Report, Chapter 6 FOIA/PA-2007-0201

IG records on named individual FOIA/PA-2007-0202
May 11, 2007 ENCLOSURE J

Office of Human Resources (HR)

Items of Interest

Week Ending May 11, 2007

Arrivals

APPLESTEIN, LISA SECRETARY (OA) NRR

BARRETT, HAROLD FIRE PROTECTION ENGINEER NRR

CUSHMAN, BRIAN REACTOR ENGINEER/RESIDENT

INSPECTOR

RIII

FLETCHER, MICHELE SECRETARY (OA) NRR

GEER, BETTY INFORMATION TECHNOLOGY SPECIALIST RI

HELM, JONATHAN REACTOR INSPECTOR (NSPDP) RII

JONES, LATOYA SECRETARY (OA) NRR

LEWIS, MONICA STUDENT ENGINEER (CO-OP) RII

NORATO, MICHAEL SR. CHEMICAL PROCESS ENGINEER NMSS

OTERO-GONZALEZ, LAURA STUDENT TRAINEE HR

PARWANI-JAIMES, TANYA SECRETARY (OA) NMSS

PASQUALE, DANIEL OPERATIONS ENGINEER NRR

ROBINSON, REBECCA SUMMER CLERK OIS

RYCYNA, JOHN MECHANICAL ENGINEER NRR

SAAH, LAUREN SECRETARY (OA) NRR

SANCHEZ, ALBA BRANCH CHIEF NRO

SARGENT, KIMBERLY DIRECTOR OF PROTOCOL OCA

TIJERINA, PATRISHA LAW CLERK OGC

WADE, TONY SECRETARY (OA) NRO

Retirement

MC COLLOCH, DONALE REFERENCE LIBRARIAN OIS
May 11, 2007 ENCLOSURE M

Office of Public Affairs (OPA)

Items of Interest

Week Ending May 11, 2007

OPA received significant media inquiries on the following:

Mercury Spill at Two White Flint: OPA worked with Montgomery County Fire Dept Public

Information Officer and followed up with local media.

SOAR-CA Study including participation from Peach Bottom and Surry Plants 

Browns Ferry restart

Indian Point license renewal and questions on recent tritium leak at site

Press Releases

Headquarters:

07-058 NRC Announces First Phase of State-of-the-Art Reactor Consequence Analysis

(5/7)

Regions:

II-07-029 NRC to Hold Public Meeting May 22 in Piketon, Ohio, to Discuss Licensing and

Inspection Program at Uranium Enrichment Plant (5/10)

II-07-030 NRC to Discuss 2006 Performance at Robinson Nuclear Plant (5/11)

II-07-031 NRC to Discuss 2006 Performance at Harris Nuclear Plant (5/11)

IV-07-014 NRC to Discuss 2006 Performance at Waterford 3 Nuclear Plant May 17 (5/10)
May 11, 2007 ENCLOSURE O

Office of the Secretary (SECY)

Items of Interest

Week Ending May 11, 2007

Document Released

to Public

Date Subject

Decision Documents

1. COMSECY-07-0007 3/1/07 Office of the Inspector General Investigation

- Security of Sensitive NRC Material

Located at Former Local Public Document

Room Libraries

SRM on 07-0007 4/4/07 (same)

Commission Voting

Record on 07-0007

4/4/07 (same)

2. SRM on SECY-07-0011 3/12/07 Interim Implementation of Fingerprinting

Requirements in Section 652 of the Energy

Policy Act of 2005

Commission Correspondence

- Letter to Congressman Bart Gordon, dated May 1, 2007, provides the requested Office of

the Inspector General report on former Local Public Document Room libraries. 

Federal Register Notices Issued

1. 10 CFR Part 51 (Docket No. PRM-51-12), State of California; Receipt of Petition for

Rulemaking, notice of receipt. 

2. Advisory Committee on Reactor Safeguards (ACRS), Subcommittee Meeting on

Thermal-Hydraulic Phenomena, revised notice of meeting (5/15-16/2007). 

3. ACRS, Meeting of the Subcommittee on Plant License Renewal, notice of meeting

(6/5/2007). 

4. ACRS, Subcommittee Meeting on Planning and Procedures, notice of meeting

(6/5/2007). 

5. Application to Amend a License to Export a Utilization Facility (Westinghouse Electric

Co.).
May 11, 2007 ENCLOSURE P

Region IV (RIV)

Items of Interest

Week Ending May 11, 2007

Wolf Creek Generating Station Annual Assessment Meeting

On May 3, 2007, Region IV staff conducted a public meeting in Burlington, Kansas, to discuss

the Wolf Creek Generating Station’s safety performance for 2006. The meeting was attended

by approximately 25 people, including state and local officials and a member of the local media.

Grand Gulf Nuclear Station Annual Assessment Meeting

On May 8, 2007, Region IV staff conducted a public meeting in Port Gibson, Mississippi, to

discuss Grand Gulf Nuclear Station’s safety performance for 2006. In addition to several

members of the public, the meeting was attended by state and local officials as well as the

media.

Announcement of Diablo Canyon Power Plant Site Vice President

On May 8, 2007, Pacific Gas and Electric Company announced that Mr. John Conway will

become the new Site Vice President at the Diablo Canyon Power Plant. Mr. Conway will

replace Mr. David Oatley who recently retired. Mr. Conway most recently served as Site Vice

President of the Monticello Nuclear Plant. Mr. Conway will assume his duties effective May 29,

2007.
May 11, 2007 

Office of Congressional Affairs (OCA)

Items of Interest

Week Ending May 11, 2007

CONGRESSIONAL HEARINGS SCHEDULE, NO. 15

OCA

Contact

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 PLACE

TIME COMMITTEE SUBJECT 

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