INFORMATION REPORT

March 15, 2004 SECY-04-0043

For: The Commissioners

From: William M. Dean, Assistant for Operations, Office of the EDO

Subject: SECY-04-0043 WEEKLY INFORMATION REPORT - WEEK 

ENDING MARCH 5, 2004

Contents Enclosure

Nuclear Reactor Regulation A

Nuclear Material Safety and Safeguards B

Nuclear Regulatory Research C

Nuclear Security and Incident Response D

General Counsel E*

Administration F

Chief Information Officer G

Chief Financial Officer H*

Human Resources I

Small Business and Civil Rights J*

Enforcement K*

State and Tribal Programs L*

Public Affairs M

International Programs N

Office of the 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 by Melinda Malloy Acting For/

William M. Dean

Assistant for Operations, OEDO

Contact:

T. Bloomer, OEDO
March 15, 2004 SECY-04-0043

For: The Commissioners

From: William M. Dean, Assistant for Operations, Office of the EDO

Subject: SECY-04-0043 WEEKLY INFORMATION REPORT - WEEK 

ENDING MARCH 5, 2004

Contents Enclosure

Nuclear Reactor Regulation A

Nuclear Material Safety and Safeguards B

Nuclear Regulatory Research C

Nuclear Security and Incident Response D

General Counsel E*

Administration F

Chief Information Officer G

Chief Financial Officer H*

Human Resources I

Small Business and Civil Rights J*

Enforcement K*

State and Tribal Programs L*

Public Affairs M

International Programs N

Office of the 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 by Melinda Malloy Acting For/

William M. Dean

Assistant for Operations, OEDO

Contact:

T. Bloomer, OEDO

DISTRIBUTION:

Central File

Public Document Name: C:\WIR\Week305.WPD

OEDO AO/OEDO

TBloomer:paa WMDean

03/15/04 03/15/04
WEEKLY INFORMATION REPORT - WEEK ENDING MARCH 5, 2004

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

Headquarters and Regional Office activities. 

Contact: T. Bloomer, OEDO by E-mail: teb@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 STP *

NMSS 4 OPA 17

RES 8 OIP 18

NSIR 9 SECY 19

OGC * Region I 20

ADM 10 Region II 21

CIO 11 Region III *

CFO * Region IV 23

HR 15 OEDO *

SBCR * OCA 24

OE *

*No input this week
March 5, 2004 ENCLOSURE A

Office of Nuclear Reactor Regulation

Items of Interest

Week Ending March 5, 2004

Kewaunee Nuclear Power Plant - Power Uprate Approved

On February 27, 2004, the NRC staff approved a request by the Nuclear Management

Company, LLC (NMC) to increase the generating capacity of the Kewaunee Nuclear Power

Plant by 6 percent. This power uprate request was approved following the staff’s safety review

and increases the generating capacity of the plant from 1673 to 1772 megawatts thermal. NMC

intends to implement the power uprate by the end of March 2004.

Seabrook Power Station - Power Uprate Public Meeting

On March 3, 2004, a Category 1 public meeting was conducted at the NRC Headquarters,

Rockville, MD between the NRC staff and representatives from Seabrook Power Station. At

this meeting Seabrook discussed with NRC staff their planned 5 percent power uprate license

amendment request submittal.

Quad Cities Unit 2 - Steam Dryer Indications

On February 24, 2004, Quad Cities Unit 2 began a refueling outage. Quad Cities Unit 2 has

had a history of steam dryer degradation since implementing an extended power uprate (EPU). 

During the outage, the licensee identified several indications of steam dryer degradation. Some

of the indications are old, and some are in areas repaired or modified in June 2003. The

licensee has sent the indication reports to General Electric (GE) for evaluation and are in the

process of providing them to the NRC. The staff will be discussing these indications and the

licensee’s dryer repair plans with the licensee once GE and the NRC have a chance to evaluate

the indication reports. Quad Cities Unit 2 operated for almost 8 months following the June 2003

dryer repairs; about 6 months of this was at full EPU power.

Meeting with the Westinghouse Owners Group to Discuss Proposed Topical Report for RiskInforming Non-Loss-of-Coolant Accident (Non-LOCA) Transients and Accidents

On March 3, 2004, the staff met with members of the Westinghouse Owners Group (WOG) to

discuss the WOG proposal to reclassify non-LOCA transients and accidents using a riskinformed approach. The staff pointed out the relationship of this proposal to the current efforts

to risk-inform the design-basis LOCA as part of the 10 CFR 50.46 rulemaking effort and the

resource constraints within the staff to review the WOG proposal at this time. As such, the staff

requested that the WOG delay further action on this initiative until resources can be made

available from the 10 CFR 50.46 rulemaking effort to focus on the WOG initiative. The WOG

agreed to delay submittal of a topical report on this issue until they have met with the staff

sometime in the future after a better understanding is available on the direction the staff is

going with regard to design basis accident redefinition.
March 5, 2004 ENCLOSURE A

Nuclear Energy Agency (NEA)/NRC Workshop on Debris Impact on Emergency Coolant

Recirculation

On February 25-27, 2004, Division of Systems Safety and Analysis staff attended an NEA/NRC

Workshop on Debris Impact on Emergency Coolant Recirculation held in Albuquerque, New

Mexico. Presentations were made by representatives from several countries on approaches

taken and results achieved to date. The NRC approach to pressurized-water reactor (PWR)

sump performance resolution was discussed. 

Meeting with North American Electric Reliability Council (NERC)

Representatives from NRR and the Office of Nuclear Regulatory Research met with NERC on

February 25, 2004, at their offices in Princeton, New Jersey. NERC is a voluntary organization

that develops operating standards for the electric power grid and monitors compliance by

control area operators. NERC discussed their short-term and long-term corrective action

program in response to the August 14, 2003 Power Outage Event.

An audit of all the large control areas is currently under way to assess compliance with the

operating standards. These audits should help to identify any systemic problems that could

contribute to a degraded grid condition. FERC is participating in these audits in an oversight

capacity. The staff emphasized the need to communicate degraded grid conditions to nuclear

plant operators.

NERC is developing a reliability functional model based on electricity markets and through the

introduction of new market players. The new model will specifically address functional duties at

each level for maintaining grid reliability. Several standards are undergoing enhancements

along with the development of a new standard for reliability and security. 

Public Meeting on Revised Order EA-03-009

On March 2, 2004, the staff held a public meeting on the revised Order (Enforcement Action

(EA) 03-009) regarding inspection requirements of reactor pressure vessel (RPV) upper heads

and associated penetrations. The revised Order refines the inspection requirements of the

original Order EA-03-009, which was issued on February 11, 2003, by incorporating new

information gained from inspections performed during the past year. Approximately 20

members of industry and the public attended the meeting, with an additional 33 individuals

participating by telephone. The NRC staff made a brief presentation introducing the changes

addressed in the revised Order, which was then followed by a question and answer session. A

summary of the meeting will be posted on the NRC’s web site that will include all of the

questions asked and the associated responses, along with general clarifications discussed

during the meeting. This summary will also be distributed to the recipients of the revised Order

to ensure that they are made aware of the topics discussed.

American Society of Mechanical Engineers (ASME) Code Meetings

NRR staff attended ASME Section III, IX, and XI Code meetings the week of February 23,

2004, in Tampa/St. Petersburg, Florida. Some of the highlights of the Section XI meetings

include: 
March 5, 2004 ENCLOSURE A

The Task Group (TG) on Boric Acid Corrosion discussed current Code requirements related to

the visual examinations associated with pressure tests of borated water systems. These

examinations are currently conducted (with some notable exceptions) with insulation in place. 

The TG developed and approved an addition to the IWB-2500 tables specifically for pressure

boundary components fabricated from Alloy 600/82/182 materials that will require direct

(i.e., bare metal) examination. The frequency of such inspections will be every refueling

outage. Performing direct visual examinations would assist in the early identification of throughwall leakage in borated water systems, which can also assist in mitigating any consequent boric

acid corrosion of ferritic materials exposed to such through-wall leakage. The TG will present

the proposed Code change to the Working Group on Inservice Inspection Optimization and the

Subcommittee for Section XI during the May 2004 Code meetings. 

The TG on Alloy 600 discussed potential changes to Code examination requirements for

reactor vessel upper head penetrations and welds. The technical basis document that forms

the basis for the proposed changes (which was developed by the industry’s Materials Reliability

Program) has not been provided to the Task Group, so no formal action on the revised

inspection requirements took place. The NRC representative, as well as the Chair of the Task

Group, stressed the importance of receiving the technical basis document by the end of March

so that Code actions may proceed during the May and August 2004 Code meetings.

License Renewal Application for Point Beach Nuclear Plant, Units 1 and 2

On February 26, 2004, the staff received from the Nuclear Management Company, Limited

Liability Corporation (LLC), the licensee for the Point Beach Nuclear Plant, Units 1 and 2, its

application requesting the extension of the operating licenses for an additional 20 years beyond

their current 40-year terms, pursuant to 10 CFR Parts 51 and 54. Point Beach Nuclear Plant,

Units 1 and 2 are pressurized-water reactors designed by Westinghouse with current operating

licenses that expire at midnight on October 5, 2010, and March 8, 2013, respectively. The staff

plans to hold a public information session near the plant on March 31, 2004, to describe the

safety and environmental reviews which will be performed, and other steps in the license

renewal process.

Nuclear Utilities Procurement Issues Committee (NUPIC) - Semi-Annual Meeting

On February 25-26, 2004, representatives of the Division of Inspection Program Management

(DIPM) attended the semi-annual meeting of NUPIC members in Myrtle Beach, South Carolina. 

The NRC conducted presentations on NRC participation on NUPIC audits, future NUPIC/NRC

interaction, and staff efforts to assess options for adopting other international quality assurance

standards (SECY-03-0117). An extensive question and answer session on several different

topics of interest to NUPIC members followed the presentation.

NRC Regulatory Issue Summary (RIS) 2004-03: Risk-Informed Approach for Post-Fire

Safe-Shutdown Associated Circuit Inspections

On March 2, 2004, the NRC staff issued the subject RIS. Beginning in 1997, a series of

licensee event reports identified plant-specific problems related to potential fire-induced

electrical circuit failures that could prevent operation or cause mis-operation of equipment

necessary to achieve and maintain hot shutdown. These problems were documented in NRC
March 5, 2004 ENCLOSURE A

Information Notice 99-17, "Problems Associated With Post-Fire Safe-Shutdown Circuit

Analysis." In 1998, the staff began interactions with stakeholders to develop an effective

risk-informed solution to the issue. Due to different stakeholder interpretations of the

regulations, the staff temporarily suspended the associated circuit portion of fire protection

inspections. This RIS clarifies the approach that will be used by the staff to perform post-fire

safe-shutdown associated circuit inspections. 
March 5, 2004 ENCLOSURE B

Office of Nuclear Material Safety and Safeguards

Items of Interest

Week Ending March 5, 2004

Kick-off Meeting for the Center for Nuclear Waste Regulatory Analyses’ Reviews of Integrated

Safety Analysis Summaries

On February 25, 2004, staff from the Division of Fuel Cycle Safety and Safeguards (FCSS) met

with the Center for Nuclear Waste Regulatory Analyses (hereafter, the Center) in San Antonio,

Texas to discuss the Center’s reviews of Integrated Safety Analysis (ISA). Since this was the

first task order on the contract involving the actual review of an ISA summary, the purpose of

the kick-off meeting was to provide the Center with information on NRC’s expectations for ISA

summary reviews. This information included regulatory framework, depth of review,

communications with NRC staff and licensees, and the format for the final product, which is a

Technical Evaluation Report.

Meeting with the Canadian Nuclear Safety Commission

On March 2, 2004, FCSS staff met with members of the Canadian Nuclear Safety Commission

(CNSC), at their request. Two CNSC licensees are planning to produce slightly enriched

uranium at their facilities, beginning in 2005-2006. FCSS staff members discussed their

experiences in licensing fuel fabrication facilities with CNSC staff responsible for licensing and

compliance of the proposed Canadian facilities. The discussion also focused on fire protection

and criticality safety -- areas of particular interest to the CNSC staff. CNSC staff also visited the

Global Nuclear Fuel-Americas facility in Wilmington, North Carolina, on March 4, 2004.

Meeting with Ministry of Economy, Trade, and Industry, and the Japanese Nuclear Energy

Safety Organization

On March 2, 2004, FCSS met with Takeshi Seino and Nobuyuki Hara, both of whom work for

the Ministry of Economy, Trade, and Industry, and with Tsuchino Susumu, who works for the

Japanese Nuclear Energy Safety Organization, at their request. The purpose of the meeting

was to discuss the staff's review of the U.S. Mixed-Oxide Fuel Fabrication Facility and to

answer questions. Before the meeting, Dr. Seino provided a questionnaire containing 40

questions in the areas of confinement, fire/explosion, criticality safety, seismicity, and electricity. 

At the outset, FCSS staff presented an overview of 10 CFR Part 70, one of the primary NRC

regulations governing the staff's safety review. FCSS staff discussed answers to the questions

contained in the questionnaire, as well as other questions posed.

Semi-Annual Meeting of the Advisory Committee on the Medical Uses of Isotopes

On March 1-2, 2004, the Director, Office of Nuclear Material Safety and Safeguards, and staff

and management of the Division of Industrial and Medical Nuclear Safety, met with the Advisory

Committee on the Medical Uses of Isotopes (ACMUI). Issues concerning implementation of the

revised 10 CFR Part 35, the proposed rulemaking on the training and experience segments of

Part 35, the licensing of emerging technology modalities, and radiation dose reconstruction for

the St. Joseph Mercy Hospital member of the public exposure case were discussed during the

publicly noticed meeting. On March 2, 2004, during the annual meeting with the Commission,
March 5, 2004 ENCLOSURE B

the ACMUI discussed the proposed training and experience amendments to Part 35 and the

St. Joseph case. 

NRC Staff Meeting on Decommissioning of Westinghouse Hematite Facility

On February 27, 2004, the Director, Division of Waste Management (DWM); Director, Division

of Nuclear Materials Safety, Region III (RIII); and staff met with the Director of the

Westinghouse Hematite Decommissioning Project and his staff. The purpose of the

management meeting was to announce a planned change in NRC project oversight

responsibilities from RIII to DWM, and to discuss Westinghouse’s proposed decommissioning

plan (DP). The Westinghouse-Hematite facility is currently undergoing decontamination

activities under approved license conditions. Westinghouse provided an overview of its current

decommissioning organization, site history and operations, past environmental studies

conducted at the site, current decontamination activities, public outreach activities, planned

licensing overview, and an outline of its proposed DP. The State of Missouri Department of

Natural Resources participated in the meeting, as well as representatives of two past site

operators. Because of the complex nature of decommissioning the site, NRC and

Westinghouse management agreed to hold a follow-up meeting soon.
March 5, 2004 ENCLOSURE C

Office of Nuclear Regulatory Research

Items of Interest

Week Ending March 5, 2004

International Workshop on Pressurized Water Reactor (PWR) Sump Performance

On February 25-27, 2004, managers and staff members from the Office of Nuclear Regulatory

Research (RES) and Nuclear Reactor Regulation (NRR) attended the International Workshop

on PWR Sump Performance co-chaired by the Committee on the Safety of Nuclear Installations

(CSNI) and the NRC, in Albuquerque, New Mexico. This workshop was the result of a RES

initiative to generate international dialog and collaboration toward resolution of this important

safety issue. Over 130 representatives from 13 countries participated in sessions on Safety

Assessment and Regulatory Requirement, Experimental Work, Analytical Work, and Industry

Solutions. Extensive discussions were held on sump performance assessment methods, plant

modifications, and operating procedures to resolve this issue. NRR and RES presented NRC’s

approach to sump performance resolution and related research in U.S., respectively.

At the workshop, the Institut de Radioprotection et de Sureté Nucleaire (IRSN) proposed and

solicited participation from the international community for an extensive test program at two

European facilities to investigate PWR debris and chemical effects, and their impact on sump

performance. The tests would be conducted through the end of 2005. RES management is

considering participation in this major international cooperative research effort. A key issue is

the ability of the international program to provide test results on a schedule to support NRC

decision making.

Release of NUREG/BR-0308, “Effective Risk Communication: The Nuclear Regulatory

Commission’s Guidelines for External Risk Communication” and NUREG/CR-6840, “The

Technical Basis for the NRC’s Guidelines for External Risk Communication”

RES, with contributions from the Risk Communications Steering Committee, recently released

NUREG/BR-0308 and NUREG/CR-6840 to provide guidance to agency staff and management

on NRC-specific communication topics and situations that deal with risk to ensure the agency's

openness with the public. NUREG/BR-0308 contains practical, how-to guidance, tailored to

NRC needs, that reflect the risk communication understanding of researchers, trainers, and

practitioners from numerous Federal, State, private, and educational organizations. 

NUREG/CR-6840 presents a comparative analysis of NRC’s risk communication needs and the

state-of-the-art in risk communication practices, with a focus on external risk communications. 

In addition to providing a resource for the data collected during the formulation of NUREG/BR0308, NUREG/CR-6840 also provides recommendations for how the NRC can best incorporate

risk communication principles throughout the agency. 

Publication: Regulatory Guide 1.200, “An Approach for Determining the Technical Adequacy of

Probabilistic Risk Assessment Results for Risk-Informed Activities”

On February 27, 2004, RES issued for trial use the subject Regulatory Guide (RG). This RG is

expected to provide the level of confidence in the technical quality of the probability risk

assessment (PRA) needed to support the identified applications such that an in-depth technical

review by NRC staff would not be needed. This RG should allow staff to focus their review on
March 5, 2004 ENCLOSURE C

key assumptions and areas identified by peer reviewers as being of concern and are relevant to

the application. Consequently, this guide is intended to provide for a more focused and

consistent review process.

Completion of Draft Report on Mitigating Systems Performance Index (MSPI) Pilot Program

A draft of the “Report on the Independent Verification of the Mitigating Systems Performance

Index (MSPI) Results for the Pilot Plants” has been completed by RES staff and was sent to

NRR on February 24, 2004. This report provides the results of the independent verification

effort for the pilot program that was initiated in the summer of 2002. The MSPI was extensively

tested, evaluated and reviewed during the pilot plant trial and evaluation period. 

Issuance of Large Early Release Frequency (LERF) Standardized Plant Analysis Risk (SPAR)

Model for First Lead Plant

RES staff has completed the SPAR model for the calculation of LERF for the first lead plant (a

Westinghouse 4-loop PWR with a large, dry containment - Comanche Peak 1 and 2). This was

sent to the licensee on February 26, 2004, in anticipation of the on site quality assurance review

against the licensee’s Level 2/LERF Probabilistic Risk Assessment model. The purpose of the

LERF SPAR Model Development Program Plan is to produce a set of SPAR models that can be

used by staff analysts to make independent LERF assessments of operational events and

conditions and other regulatory issues under the guidance specified in Regulatory Guide 1.174. 

RES is initially developing LERF models for lead plants in ten plant classes. 
March 5, 2004 ENCLOSURE D

Nuclear Security and Incident Response

Items of Interest

Week Ending March 5, 2004

Preliminary Notifications

1. PNO-I-04-009, Yankee Atomic Electric Company - SPILL OF LOW-LEVEL

RADIOACTIVE WASTE FROM PACKAGE WHILE IN TRANSIT.

2. PNO-I-04-008, St. Mary Hospital - POTENTIAL MEDICAL EVENT INVOLVING A

PROSTATE SEED IMPLANT.

3. PNO-IV-04-008, Altru Health System - MEDICAL EVENT - RADIATION DOSE TO AN

UNINTENDED SITE.

4. PNO-IV-04-009, Arizona Public Service Company - SHUTDOWN OF UNIT 3 FOR

GREATER THAN 72 HOURS.
March 5, 2004 ENCLOSURE F

Office of Administration 

Items of Interest 

Week Ending March 5, 2004

Contract Awards

A competitive firm fixed-price/requirements-type contract (number NRC-03-04-027) was

awarded to Anbex Inc. of Branchville, New Jersey on March 5, 2004, for the purchase of

potassium iodide (KI) tablets. The period of performance is two years with three one-year

option periods. The total estimated price of the contract, inclusive of option years, is

$1,545,246.88. The staff issued several streamlining initiatives, including issuing a combined

synopsis/solicitation, establishing a deadline for receipt of proposers’ questions, applying

simplified evaluation criteria, and using only one source evaluation panel member. 

A competitive fixed-price delivery order (number DR-09-04-305) was awarded to Management

Concepts of Vienna, Virginia on March 2, 2004, for “Management Control Training.” The period

of performance is one year with four one-year option periods. The total contract ceiling,

inclusive of option years, is $337,306.
March 5, 2004 ENCLOSURE G

Chief Information Officer

Items of Interest

Week Ending March 5, 2004

Freedom of Information Act and Privacy Act Requests received during the period of

February 27 through March 4, 2004:

Allegation RIV-96-A-0287, all documents including correspondence

between named individual and NRC

FOIA/PA-2004-0143

General index of released records, description of agency

organization, and administrative staff manuals

FOIA/PA-2004-0144

NRC’s Fiscal Year 2005 Exhibit 300s FOIA/PA-2004-0145

Operator License No. SOP-31197, copy of expiration notice FOIA/PA-2004-0146

Institutions that specialize in medical imaging FOIA/PA-2004-0147

Security file on named individual FOIA/PA-2004-0148

Curtis Wright Corporation, Buffalo, New York, licenses, inspections &

contracts

FOIA/PA-2004-0149

Air Force Plant 49 (former), Grider Street, Buffalo, NY, licenses,

inspections & subcontracts

FOIA/PA-2004-0150

Curtis Wright or Wright Aeronautical Facility, 300 Fairfield Avenue,

Fairfield, New Jersey, licenses, inspections or subcontracts

FOIA/PA-2004-0151

Complaint/communications from named individual re: Palisades

Nuclear Power Plant

FOIA/PA-2004-0152
March 5, 2004 ENCLOSURE I

Office of Human Resources

Items of Interest

Week Ending March 5, 2004

Arrivals

James Baptist Project Engineer R-II

Diane Corlew Secretary (OA) R-I

Patricia Garrett Secretary (OA) R-I

Thomas Hafera Reactor Systems Engineer NRR

Deonna Hester Secretary (OA) HR/SPAC

April Leoffler Secretary (OA) HR/SPAC

Jay Thompson Health Physicist NMSS

Christopher M. Wachter Law Clerk Intern ASLBP

Donald Williams, II Program Analyst OCFO

Retirements

Nancy B. Holbrook Management & Program Analyst R-IV

Darl S. Hood Sr. Project Manager NRR

Departures

William Franz Criminal Investigator R-III

Carl A. Fredericks Sr. License Fee Analyst OCFO
March 5, 2004 ENCLOSURE M

Office of Public Affairs

Items of Interest

Week Ending March 5, 2004

Media Interest

The Office of Public Affairs (OPA) responded to significant media inquiries on the following:

Media interest continued in efforts by FirstEnergy to win NRC approval to restart the DavisBesse nuclear plant. OPA HQ facilitated an interview of NRR’s Brian Sheron by the Dow-Jones

News Wires on lessons learned from Davis-Besse; 

There was media interest in public participation opportunities for the Vermont Yankee power

uprate request; and 

OPA fielded numerous media calls about the special inspection at the Palo Verde nuclear plant,

as well as the discovery there of boron deposits on a reactor vessel. 

Other Public Affairs Items

OPA supported a scoping meeting of about 250 people in Eunice, New Mexico, for an

environmental impact statement on a proposed uranium enrichment plant; and

OPA supported the Commission’s public meeting on the coming anniversary of the Three Mile

Island 2 accident in 1979 and fielded several related media calls. 

Press Releases

Headquarters:

04-029 NRC Announces Availability of License Renewal Application for Point

Beach Nuclear Power Plant (3/1)

04-030 NRC Approves Power Uprate for Kewaunee Nuclear Power Plant (3/2)

04-031 NRC Issues Annual Assessments for Nation’s Nuclear Plants (3/5)

Regions:

I-04-007 NRC Proposes $3,000 Fine Against VA Firm Over Temporary Loss of

Nuclear Gauge (3/3)

IV-04-007 NRC to Conduct Special Inspection at Palo Verde Nuclear Generating

Station (3/1)

IV-04-008 NRC to Hold Regulatory Conference with Entergy Operations on Waterford

Nuclear Power Plant (3/2)
March 5, 2004 ENCLOSURE N

Office of International Programs

Items of Interest

Week Ending March 5, 2004

Japanese Visit to Discuss Safety Evaluation of Mixed Oxide (MOX) Facility

On March 2, 2004, a Japanese regulatory team from the Nuclear and Industrial Safety Agency

(NISA) and the Japan Nuclear Energy Safety Organization (JNES) met with staff from NMSS to

discuss the safety evaluation criteria for an MOX fuel manufacturing facility. NISA is developing

its evaluation criteria for the MOX fuel fabrication facility under construction at Rokkasho-Mura,

and the experimental facility at Tokai-Mura that will become an industrial facility.
March 5, 2004 ENCLOSURE O

Office of the Secretary

Items of Interest

Week Ending March 5, 2004

Document Released

to Public

Date Subject

Decision Documents

1. SECY-04-0008 1/26/04 Proposed Amendment to Agreement

Between the State of Utah and the

Commission Pursuant to Section 274 of the

Atomic Energy Act of 1954, as Amended

SRM on SECY-04-0008 2/6/04 (same)

Commission Voting

Record on SECY-04-

0008

2/6/04 (same)

Information Papers

1. SECY-04-0036 3/3/04 SECY-04-0036 Weekly Information Report -

Week Ending February 20, 2004

2. SECY-04-0038 3/4/04 SECY-04-0038 Weekly Information Report -

Week Ending February 27, 2004

Memoranda

1. M040302A 3/2/04 Staff Requirements - Affirmation Session:

I. SECY-04-0023-Private Fuel Storage

(Independent Spent Fuel Storage

Installation) Docket No. 72-22-ISFSI;

II. SECY-04-0028-Requests for Application

of New Part 2 Rules to Early Site Permit

Hearings in North Anna, Clinton, and Grand

Gulf

2. M040218B 3/2/04 Staff Requirements - Briefing on Office of

Chief Financial Officer Programs,

Performance, and Plans

Commission Correspondence

1. Letter to David Lochbaum, Union of Concerned Scientists and Shari Weir, Ohio Citizen

Action, dated February 25, 2004, responds to letter requesting the Commission conduct a

public meeting prior to the restart of Davis-Besse.
March 5, 2004 ENCLOSURE O

2. Letter to Congresswoman Velázquez, dated February 24, 2004, concerns the Radiac

Research Corp. facility in Brooklyn, New York. 

3. Letter to Olene Walker, Governor of Utah, concerns the regulatory authority over the

possession and use of 11e(2) byproduct material.

Federal Register Notices Issued

1. Advisory Committee on Reactor Safeguards Joint Meeting of the Advisory Committee on

Reactor Safety Subcommittees on Reliability and Probabilistic Risk Assessment and on

Plant Operations (3/25/04).

2. Advisory Committee on Reactor Safeguards Meeting of the Subcommittee on Plant

Operations (3/26/04).

3. Advisory Committee on the Medical Uses of Isotopes: Meeting Notice (3/22/04).
March 5, 2004 ENCLOSURE P

Region I

Items of Interest

Week Ending March 5, 2004

Tennessee Integrated Materials Performance Evaluation Program (IMPEP) Review

On February 23-26, 2004, an IMPEP review of the Tennessee Agreement State Program was

conducted by staff from Region I, Region III, the Offices of State and Tribal Programs, Nuclear

Materials Safety and Safeguards, and the State of Maine. This review focused on the State’s

performance over the last four years for seven performance indicators and the State’s actions

taken in response to recommendations made during the previous IMPEP reviews conducted in

August 2000 and October 2001. The Region I Director, Division of Nuclear Materials Safety,

attended the exit meeting. The IMPEP Team will draft its report and meet with the NRC

Management Review Board. 

Maine Yankee Completes Transfer of Spent Fuel to Onsite Independent Spent Fuel Storage

Installation (ISFSI)

On February 27, 2004, Maine Yankee transferred the final spent fuel storage canister to its

onsite ISFSI. The completion of the fuel transfer project allows Maine Yankee to perform final

cleaning and surveys in the spent fuel pool, commence draining the pool, remove fuel racks,

and demolish the spent fuel pool and control room. Control Room and security functions have

been transferred to facilities at the ISFSI. As a result of the transfer of all fuel to the ISFSI,

NRC rescinded the May 23, 2002, Order for Interim Safeguards and Security Compensatory

Measures (ICMs) in effect at Maine Yankee. The ICMs applied to decommissioning nuclear

power plants with spent fuel in the spent fuel pool. The October 16, 2002, Maine Yankee Order

for ICMs at the ISFSI remains in effect.
March 5, 2004 ENCLOSURE P

Region II

Items of Interest

Week Ending March 5, 2004

South Carolina Electric and Gas Company - V. C. Summer Visit

On March 2, 2004, the Regional Administrator visited the V. C. Summer Nuclear Plant in

Columbia, South Carolina. The purpose of the visit was to tour the facility and meet with

licensee management and the resident inspectors. 

Westinghouse Fuel Fabrication Facility - Canadian Nuclear Safety Commission Visit

On March 2, 2004, the Director, Processing Facilities and Technical Support Division, of the

Canadian Nuclear Safety Commission (CNSC) and two of his staff members toured the

Westinghouse Fuel Fabrication Facility in Columbia, South Carolina.

On March 3, 2004, the Regional Administrator, and the Director, Division of Fuel Facility

Inspection attended a public meeting with Westinghouse management in Columbia, South

Carolina. The purpose of the meeting was to discuss the results of the Licensee Performance

Review. The CNSC representatives observed the public meeting

Duke Energy Corporation - Oconee Predecisional Enforcement Conference

On March 2, 2004, representatives from Duke Energy Corporation were in the Regional Office

to attend a Predecisional Enforcement Conference. The purpose of the meeting was to discuss

an apparent violation of 10 CFR 50.59. 

Duke Energy Corporation - Catawba Emergency Exercise Preparation

On March 4, 2004, representatives from the Duke Energy Corporation were in the Region II

Office to give an overview of the Catawba Emergency Exercise. The exercise is scheduled for

March 16. The NRC is participating with a Regional Base Team, Regional Site Team and a full

Headquarters Team. The Regional Administrator is participating as the Site Team

Leader/Director of Site Operations.
March 5, 2004 ENCLOSURE P

Region IV

Items of Interest

Week Ending March 5, 2004

Public Meeting With Nebraska Public Power District - Cooper Nuclear Station

On March 1, 2004, Region IV conducted a meeting with Nebraska Public Power District (NPPD)

in Arlington, Texas. Topics discussed during the meeting included NPPD’s implementation of

their performance improvement plan at Cooper Nuclear Station; NPPD’s progress in completing

the actions specified in the Confirmatory Action Letter dated January 30, 2003; and the criteria

for assessing closure of the actions specified in the Confirmatory Action Letter. 

Special Inspection Conducted at Palo Verde Nuclear Station

During the week of March 1-5, 2004, representatives from Region IV and the Office of Nuclear

Reactor Regulation conducted a special inspection at the Palo Verde nuclear station. The team

evaluated two operational issues occurring in the Unit 2 reactor facility: gas entrainment in the

shutdown coolant system during reduced inventory operation, and leakage of coolant from the

primary to the secondary side of one of the new Unit 2 steam generators. 
March 5, 2004 

Office of Congressional Affairs

Items of Interest

Week Ending March 5, 2004

CONGRESSIONAL HEARING SCHEDULE, NO. 48

OCA

Contact

DATE &

PLACE

TIME WITNESS SUBJECT 

Portner 03/11/04

2362B RHOB

10:00 DOE FY05 Budget Reps. Ho

Energy anAppropria

Gerke March 2004

TBA

TBA DOE Final Report by U.S. - Canada

Power System Outage Task Force 

Senators Energy an

Long 03/17/04

2362B RHOB

10:00 DOE FY05 Nuclear Energy Budget Reps. Ho

Energy anAppropria

Gerke 03/17/04

2203 RHOB

10:00 Ellis Merschoff, OMB,

GAO, DOJ, DOL, HHS,NIST, and Treasury

Agencies’ Computer Security Efforts Reps. Pu

TechnolotergovernCensus G

Combs 03/24/04

2362B RHOB

10:00 DOE FY05 Nuclear Waste Budget Reps. Ho

Energy anAppropria

Portner 04/29/04

TENTATIVE

TBA NRC Commissioners NRC Oversight Senators 

Clean AirNuclear SEnvironm