INFORMATION REPORT

April 16, 2007 SECY-07-0072

For: The Commissioners

From: Michael R. Johnson, Assistant for Operations, Office of the EDO

Subject: WEEKLY INFORMATION REPORT - WEEK ENDING

APRIL 6, 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/

Michael R. Johnson 

Assistant for Operations, OEDO

Contact:

L. Rakovan, OEDO
April 16, 2007 SECY-07-0072

For: The Commissioners

From: Michael R. Johnson, Assistant for Operations, Office of the EDO

Subject: WEEKLY INFORMATION REPORT - WEEK ENDING

APRIL 6, 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/

Michael R. Johnson

Assistant for Operations, OEDO

Contact:

L. Rakovan, OEDO

DISTRIBUTION:

EDO R/F

AO R/F Document Name: C:\WIR\week406.WPD

OEDO AO/OEDO

LRakovan:paa MRJohnson

04/16/07 04/17/07
WEEKLY INFORMATION REPORT - WEEK ENDING APRIL 6, 2007

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

Headquarters and Regional Office activities. 

Contact: L. Rakovan, OEDO by E-mail: ljr2@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 1 OE *

NRO 2 OPA 10

NMSS 3 OIP *

FSME 4 SECY 11

RES 5 Region I *

NSIR 6 Region II 12

ADM 7 Region III *

OIS 8 Region IV 14

CFO * EDO *

HR 9 OCA *

SBCR *

*No input this week
April 6, 2007 ENCLOSURE A

Office of Nuclear Reactor Regulation (NRR)

Items of Interest

Week Ending April 6, 2007

Staff Issuance of Confirmatory Action Letters Regarding Dissimilar Metal Butt Welds

During the period of March 15 through March 29, 2007, the staff issued confirmatory action

letters (CALs) to the licensees for Diablo Canyon, Palo Verde, V.C. Summer, Waterford, St.

Lucie, Catawba, Beaver Valley, Davis Besse, Comanche Peak, Braidwood, Byron, Three Mile

Island, McGuire, San Onofre, Shearon Harris, South Texas Project, Crystal River, Millstone,

Oconee, Prairie Island, Arkansas Nuclear One, Callaway, North Anna, Palisades, and

Sequoyah. The letters confirm commitments made by the licensees to inspect the pressurizer

surge, spray, safety, and relief nozzle welds by December 31, 2007, to implement enhanced

reactor coolant system leakage monitoring until the inspections are complete, to repeat butt

weld examinations every 4 years until the welds are either removed from service or mitigated,

and to report inspection results to the NRC. 

Audit Conducted at Oconee Nuclear Station

During the week of March 26, 2007, NRR staff visited the Oconee Nuclear Station site near

Clemson, South Carolina. The purpose of the visit was to audit Duke Energy’s sump

performance corrective actions for Generic Letter 2004-02, “Potential Impact of Debris

Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water

Reactors.” The audit team conducted numerous meetings with Duke Energy’s technical

representatives, and will continue to review information provided by the licensee. NRR is

developing a report which will document the areas reviewed and open items identified, and will

continue to audit selected plants to monitor corrective actions as it works toward the resolution

of Generic Safety Issue 191.

Meeting with Federal Energy Regulatory Commission

On March 28, 2007, representatives of Federal Energy Regulatory Commission (FERC) and

NRC staff met at FERC to discuss the scope of the FERC final rule on reliability. Discussions

focused on what reliability standards that affect nuclear power plants are to be approved, what

modifications have been directed in response to the NRC’s December 21, 2006 comments

(ML063560130) to FERC’s Federal Register Notice and Mandatory Reliability Standards for the

Bulk Power System (71 FR64770). The NRC comments were limited to those standards that

could have significant planning and operating impacts on either the auxiliary power system or

the offsite power system of a nuclear power plant. The NRC staff toured the FERC operations

center where FERC monitors electric power market and bulk electric power flows. 

Boiling Water Reactor Vessel and Internals Project

On March 29, 2007, NRC staff met with members of the Boiling Water Reactor Vessel and

Internals Project (BWRVIP) to discuss various topical report reviews that are currently being

reviewed by the NRC. The subjects discussed included steam dryer integrity evaluation

updates, vessel internals inspection guidelines, mitigation activities (water chemistry and

mitigation effectiveness of core shroud reinspection data) and preliminary results of testing
April 6, 2007 ENCLOSURE A

concerning crack growth and fracture toughness of irradiated stainless steels. The NRC staff

provided comments on the subjects presented by the BWRVIP. The BWRVIP will consider the

NRC comments in their development of their topical reports, such as the generic steam dryer

report, and visual inspection guideline reports. 

On March 30, 2007, NRC management met with the BWRVIP executive members to discuss

the BWRVIP approach to management of materials degradation issues, the status of the

BWRVIP topical report reviews and the BWRVIP's future plans and submittals. The NRC will

use this information to prioritize and assess future reviews. In addition, the BWRVIP provided

the status of the evaluation on the effects of the dissimilar metal weld experience at Duane

Arnold. The BWRVIP plans to provide an initial summary of the data collected from all BWR

plants concerning the Duane Arnold issue by mid-April.

Oyster Creek Nuclear Plant Safety Evaluation Report

On March 30, 2007, the staff issued the Safety Evaluation Report (SER) related to the license

renewal of the Oyster Creek Generating Station, on schedule. By letter dated July 22, 2005,

AmerGen Energy Company, LLC, submitted an application pursuant to 10 CFR Part 54, to

renew the operating license for an additional 20 years. The NRC staff has closed all open

items and identified no confirmatory items in its review. The staff will add a total of seven new

license conditions based on staff review and Advisory Committee on Reactor Safeguards

recommendations.

Vermont Yankee Nuclear Plant Safety Evaluation Report

On March 30, 2007, the staff issued the Safety Evaluation Report (SER) with Confirmatory

Items related to the License Renewal of Vermont Yankee Nuclear Power Station. On

January 27, 2006, the staff received from Entergy Nuclear Operation, Inc., an application

requesting the extension of the operating license for Vermont Yankee Nuclear Power Station

for an additional 20 years. The SER has six confirmatory items (regarding the license renewal

scoping boundaries for various systems). The staff is scheduled to meet with the Advisory

Committee on Reactor Safeguards Subcommittee on June 5, 2007, to discuss the SER with

Confirmatory Items.
April 6, 2007 ENCLOSURE B

Office of New Reactors (NRO)

Items of Interest

Week Ending April 6, 2007

Regulatory Guide 1.189, “Fire Protection for Nuclear Power Plants”

On March 28, 2007, Revision 1 of Regulatory Guide 1.189 was issued. This revision added

guidance for new reactor fire protection programs.

Grand Gulf Early Site Permit Signing Ceremony

On April 5, 2007, the Director of NRO signed the Grand Gulf Early Site Permit. The previous

week, the Commission approved the issuance of an Early Site Permit for the Grand Gulf site,

the second time that the Commission has approved the issuance of an Early Site Permit

request. The first Early Site Permit, for the Clinton site, was approved in March 2007.
April 6, 2007 ENCLOSURE C

Office of Nuclear Material Safety and Safeguards (NMSS)

Items of Interest

Week Ending April 6, 2007

Decision on Differing Professional Opinion on Red Oil Events at the Proposed Mixed-Oxide

Fuel Fabrication Facility Issued

On March 23, 2007, the NMSS Director issued his decision on a Differing Professional Opinion

(DPO) on Red Oil Events at the Proposed Mixed-Oxide (MOX) Fuel Fabrication Facility (DPO2005-002). The Director agreed with the DPO Panel Report, which was prepared in

accordance with Management Directive 10.159. Specifically, the Director agreed that the

construction authorization for the MOX Fuel Fabrication Facility does not have to be revisited. 

The applicant for the facility has committed to provide additional information regarding its

proposed approach for controlling red-oil events, in support of the review of the Operating

License application. As part of the Operating License application review process, it is the

applicant's responsibility to demonstrate adequate protection of the public health and safety and

the environment, with respect to preventing or mitigating red-oil runaway reactions.

BWX Technologies, Inc. License Renewal

On March 29, 2007, the staff issued a renewal of the BWX Technologies, Inc. license for 20

years. This renewal period is consistent with the guidance provided by the Commission in Staff

Requirement’s Memorandum (SRM) 06-0186, dated September 26, 2006, and is the first fuel

facility license renewal issued for more than 10 years.

Public Meeting with Packaging Technology to Discuss the TRUPACT-III Full-Scale Drop-Test

Results

On March 29, 2007, the staff met with representatives from Packaging Technology, Inc. (Pac

Tec) to discuss the test results for the full-scale model of the redesigned TRUPACT-III

transportation package. This package will be used to transport transuranic waste. Discussions

focused on the drop test required by 10 CFR 71.73, “Hypothetical accident conditions.” After

each drop, a vacuum test was performed to check the integrity of the containment. After the

last drop, the full-scale model did not pass the vacuum test. Subsequent examination of the

test unit indicated that debris from the simulated contents had entered into the seal region. As

a result, Pac Tec is proposing to add a debris seal to the design. Pac Tec stated that it is

planning to submit the application in May 2007.
April 6, 2007 ENCLOSURE D

Office of Federal and State Materials and Environmental Management Programs (FSME)

Items of Interest

Week Ending April 6, 2007

Pennsylvania Request to Become an Agreement State

On March 29, 2007, staff issued a letter to the Commonwealth of Pennsylvania, documenting

the results of the staff review of Pennsylvania's response to the NRC staff’s comment letter,

which documented the results of Pennsylvania’s formal request to become an Agreement State.

Pennsylvania's response addressed the two significant issues identified by the NRC staff, which

included staffing levels and staff training and qualifications. The NRC staff plans to confirm,

through continued interactions, the information and assurances provided by Pennsylvania. 
April 6, 2007 ENCLOSURE E

Office of Nuclear Regulatory Research (RES)

Items of Interest

Week Ending April 6, 2007

Public Meeting of the NRC Digital Instrumentation and Control (I&C) Steering Committee with

Representatives of the Industry

On March 26, 2007, RES staff and industry representatives met to facilitate communication in

the areas of digital I&C and human factors and to identify and track resolution of technical and

regulatory issues for new and operating nuclear power plants. The revised structure for the

NRC’s Digital I&C Project Plan was presented and discussed. Schedule and budget concerns

were also discussed. NEI indicated concern that NRC’s requests for information concerning

digital systems may be excessive. 

Briefing by SIMCO Technologies Inc., Quebec, Canada, on Their Concrete and Cementitious

Materials Degradation Computer Code STADIUM

On March 28, 2007, RES staff and other participants, including from the Department of Energy,

were briefed regarding STADIUM. The STADIUM code, based in part on work completed by

National Institute of Standards and Technology under contract to the NRC, calculates the

transport of multiple ionic species in cementitious materials. It provides engineers with a tool

that could assist in designing and assessing new concrete structures and cementitious grouts

and in planning repair strategies for existing structures. Developed by a consortium of

organizations, including federal agencies and universities, the code is already in use

domestically and internationally in the design of large concrete structures. RES is evaluating

the use of STADIUM code in reviews and applications of specific interest to the NRC.

Public Meeting between Nuclear Energy Institute (NEI), the Electric Power Research Institute

(EPRI), and the NRC on Industry’s Plans to Develop Guidance for Implementing 10

CFR20.1406, “Minimization of Contamination”

On March 28, 2007, staff met with representatives of NEI, and EPRI to exchange information

on the progress of guidance development regarding 10 CFR 20.1406, “Minimization of

Contamination.” EPRI described ground-water protection efforts for advanced power plant

designs, and RES staff discussed the current status of technical basis development for a

regulatory guide on implementation of 10 CFR 20.1406. Current plans are to have a draft

regulatory guide ready for internal NRC review late in April 2007, followed by a public comment

period beginning in July 2007. 

Public Meeting of Task Working Group (TWG) Designated by the Digital I&C Steering

Committee to Address the Subject of Digital System Communications that Involve Equipment

Assigned to Different Safety Divisions

On March 29, 2007, an NRC Task Working Group (TWG) discussed issues related to licensing

digital I&C systems in new and operating nuclear power plants and fuel facilities. Changes to

the project plan were discussed to bring the plan into conformance with the latest format

established by the NRC’s Digital I&C Steering Committee. The role of the designated industry

participants as advisors, rather than TWG members, was clarified. A list of priorities for
April 6, 2007 ENCLOSURE E

consideration by the TWG was proposed by the industry advisors and finalized. Industry

participants described interchannel communications considerations and provisions for a

particular digital platform, and for video display units that might be used for multiple safety

divisions and for nonsafety control influence over safety-related equipment. Restrictions on

safety/nonsafety interactions were also discussed extensively. 
April 6, 2007 ENCLOSURE F

Office of Nuclear Security and Incident Response (NSIR)

Items of Interest

Week Ending April 6, 2007

Preliminary Notifications

1. PNO-II-07-003, Brunswick Steam Electric Plant, PLANT SHUTDOWN REQUIRED BY

TECHNICAL SPECIFICATIONS - BRUNSWICK UNIT 1

2. PNO-IV-07-003 Union Electric Company, Callaway Plant, CALLAWAY ALERT

DECLARATION DUE TO A SUSPECTED TRANSFORMER FIRE
April 6, 2007 ENCLOSURE G

Office of Administration (ADM)

Items of Interest 

Week Ending April 6, 2007

Industry Codes and Standards (AH76-Part 50)

On April 5, 2007, the NRC published a proposed rule in the Federal Register (72 FR 16731)

that would amend requirements adopted from industry codes and standards (AH76-Part 50). 

The proposed rule would incorporate by reference the 2004 Edition of Section III, Division 1 and

Section XI, Division 1 of the American Society of Mechanical Engineers (ASME) Boiler and

Pressure Vessel Code. The proposed rule would also incorporate by reference the 2004

Edition of the ASME Code for Operation and Maintenance of Nuclear Power Plants. The

incorporation of new editions of the ASME Code is intended to ensure the continued safe

operation of nuclear reactors. The comment period for this action closes June 19, 2007. 
April 6, 2007 ENCLOSURE H

Office of Information Services (OIS)

Items of Interest

Week Ending April 6, 2007

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

of March 30 through April 5, 2007:

Leaks of water containing tritium and Strontium-90 from Indian Point

NPP into groundwater, all correspondence between NRC and Entergy

Nuclear Northeast LLC and any New York State agencies between

January 12, 2007 and April 2, 2007

FOIA/PA-2007-0166

MLTS database, active and retire facilities FOIA/PA-2007-0167
April 6, 2007 ENCLOSURE J

Office of Human Resources (HR)

Items of Interest

Week Ending April 6, 2007

Arrivals

DUDLEY, NOEL SENIOR STAFF ENGINEER ACRS

FAIR, JOHN SENIOR MECHANICAL ENGINEER NRR

GILMAN, JOSEPH PARALEGAL SPECIALIST OGC

JONES, HENRY HYDROLOGIST NRR

VAN DOORN, PETER SENIOR REACTOR INSPECTOR RIII

Retirements

DUDLEY, NOEL SENIOR PROJECT MANAGER NRR

FAIR, JOHN SENIOR MECHANICAL ENGINEER NRR

ROSSBACH, LAWRENCE PROJECT MANAGER NRR

TSE, ANTHONY SENIOR PROJECT MANAGER FSME

Departure

SHAFFER, ROMAN INSTRUMENTATION AND CONTROL

ENGINEER

RES
April 6, 2007 ENCLOSURE M

Office of Public Affairs (OPA)

Items of Interest

Week Ending April 6, 2007

OPA received significant media inquiries on the following:

Indian Point Unit 3 shutdown/restart data; siren testing and failures; transformer fire.

NRC’s preparations for new reactor applications, licensing process and design certifications.

Issuance of the Final Safety Evaluation Report on Oyster Creek; status of license renewal

application.

Corrosion issues discussed, triggered by Exponent’s report on crack growth rates for Davis

Besse with the New York Times; The Plain-Dealer, Toledo Blade, and Platts.

Inquires into Commissioner McGaffigan’s withdrawal of his resignation letter. 

Other Public Affairs Items:

OPA Regional staff assisted in numerous end-of cycle meetings.

Press Releases

Headquarters:

07-043 NRC to Hold Public Meeting in Aiken, S.C., on License Review Process for Mox

Fuel Fabrication Facility (4/4)

07-044 NRC Staff Approves Transfer of Palisades Operating License (4/6)

Regions:

I-07-013 NRC to Discuss 2006 Assessment for Three Mile Island Nuclear Plant at Public

Meeting Scheduled for April 11 (4/4)

I-07-014 NRC Following Up On Unusual Event At Indian Point 3 (4/6)

II-07-007 NRC Schedules Regulatory Conference and Management Meeting to Discuss

Brunswick Nuclear Plant (4/3) 

II-07-008 NRC to Hold Public Meeting at Sweetwater on April 9 to Discuss 2006

Performance at Watts Bar Nuclear Power Plant (4/4)

II-07-009 NRC to Discuss 2006 Performance at Sequoyah Nuclear Power Plant (4/4)

II-07-010 NRC to Discuss 2006 Performance at Vogtle Nuclear Plant (4/5)

II-07-011 NRC to Discuss 2006 Performance at Oconee Nuclear Plant (4/5)
April 6, 2007 ENCLOSURE M

II-07-012 NRC Schedules Conference With Areva To Discuss Apparent Violations At Its

Richland, Wash. Fuel Facility(4/6)

III-07-012 NRC to Discuss 2006 Performance Assessment for Lasalle Nuclear Power Plant

(4/5)

III-07-013 NRC to Discuss 2006 Performance Assessment for D.C. Cook Nuclear Power

Plant (4/6)
April 6, 2007 ENCLOSURE O

Office of the Secretary (SECY)

Items of Interest

Week Ending April 6, 2007

Document Released

to Public

Date Subject

Decision Documents

1. SECY-07-0052 3/19/07 Nuclear Regulatory Commission Drug-Free

Workplace Plan - Recommended Testing

Rate

2. COMPBL-07-0001 3/8/07 Development of a U.S. Digital

Instrumentation and Control and HumanMachine Interface Test Facility

SRM for COMPBL-07-

0001

4/5/07 (same)

Voting Record for

COMPBL-07-0001

3/28/07 (same)

3. SRM-SECY-07-0052 4/5/07 NRC Drug-Free Workplace Plan -

Recommended Testing Rate

Voting Record - SECY07-00524/5/07 (same)

Information Papers

- SECY-07-0059 3/29/07 Weekly Information Report - Week Ending

March 23, 2007

Memoranda

- M070320 4/5/07 Briefing on Office of Information Services

(OIS) Programs, Performance, and Plans

Commission Correspondence

1. Letter to Senator Barbara Boxer, dated April 1, 2007, responds to letter regarding NRC’s

development of security requirements for new reactors.

2. Letter to Senator Barbara Boxer, dated April 1, 2007, responds to letter regarding views

about the final rulemaking to amend Title 10 of CFR Part 73.1, the Design Basis Threat

(DBT).

3. Letter to Congress, dated March 28, 2007, reporting information in this letter concerning

agency acquisitions related to “Buy American.”
April 6, 2007 ENCLOSURE O

Federal Register Notices Issued

- 10 CFR Part 73, Docket No. PRM-73-13, Union of Concerned Scientists; Receipt of

Petition for Rulemaking.
April 6, 2007 ENCLOSURE P

Region II (RII)

Items of Interest

Week Ending April 6, 2007

Brunswick Nuclear Plant Category One Regulatory Conference and Management Meetings

On April 5, 2007, representatives from Carolina Power and Light Company attended a

Regulatory and Management Meeting in the Region II office. The purposes of the meetings

were to discuss the trip of the Brunswick emergency diesel generator (EDG #1), failure of the

engine crankshaft bearing and to discuss site and EDG improvements.
April 6, 2007 ENCLOSURE P

Region IV (RIV)

Items of Interest

Week Ending April 6, 2007

Palo Verde Public Meeting

On April 3, 2007, the Regional Administrator and Deputy Executive Director for Reactor and

Preparedness Programs, as well as Headquarters and Region IV staff conducted a public

meeting in Avondale, Arizona, to discuss Palo Verde Nuclear Generating Station’s safety

performance for 2006. Participants included Arizona Public Service Company officials, NRC

staff, three members of the Arizona Corporation Commission, local community leaders, and

numerous members of the public.

Arizona Corporation Commission Meeting

On April 4, 2007, the Regional Administrator met with the Arizona Corporation Commission, at

their request, to discuss the safety performance of the Palo Verde Nuclear Generating Station. 

In addition, the Regional Administrator answered questions concerning high level waste

storage, transportation of radioactive material, radioactive waste reprocessing, and future

nuclear power plant development. Several members of the local press attended the meeting. 

The Arizona Corporation Commission has jurisdiction over the quality of service and rates

charged by public service utilities, such as Arizona Public Service Company.