INFORMATION REPORT

October 24, 2003 SECY-03-0179

For: The Commissioners

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

Subject: SECY-03-0179 WEEKLY INFORMATION REPORT - WEEK 

ENDING OCTOBER 17, 2003

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 & 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:

L. Roche, OEDO
October 24, 2003 SECY-03-0179

For: The Commissioners

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

Subject: SECY-03-0179 WEEKLY INFORMATION REPORT - WEEK 

ENDING OCTOBER 17, 2003

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 & 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:

L. Roche, OEDO

DISTRIBUTION:

Central File

Public Document Name: C:\WIR\WeekO17.WPD

OEDO AO/OEDO

LRoche:paa WMDean

10/23/03 10/24/03
WEEKLY INFORMATION REPORT - WEEK ENDING OCTOBER 17, 2003

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

Headquarters and Regional Office activities. 

Contact: L. Roche, OEDO by E-mail: lar2@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 IP *

NSIR 9 SECY 19

OGC * Region I *

ADM 10 Region II 21

CIO 11 Region III *

CFO * Region IV 23

HR 15 OEDO *

SB/CR * OCA 24

OE *

*No input this week
October 17, 2003 ENCLOSURE A

Office of Nuclear Reactor Regulation

Items of Interest

Week Ending October 17, 2003

Calvert Cliffs Nuclear Power Plant Notice of Enforcement Discretion (NOED)

On October 10, 2003, regional enforcement discretion was granted to the Calvert Cliffs Nuclear

Power Plant for a shutdown limiting condition for operation related to the 2A emergency diesel

generator (EDG). The NOED extended the 72-hour allowed outage time for an inoperable EDG

to 144 hours. 

On October 8, 2003, the 2A EDG was declared inoperable after the licensee found metallic

material in the lube oil strainer during preplanned maintenance. The apparent cause of the

bearing degradation was a distorted bearing cap. The bearing cap was believed to have been

distorted in 1995 when its bearing overheated. 

The licensee completed repairs and declared the 2A EDG operable on October 14, 2003.

Catawba Nuclear Station Unit 1 Notice of Enforcement Discretion (NOED)

On October 6, 2003, while installing inspection ports in the 1B Containment Spray System

(CSS) heat exchanger in preparation for future maintenance activities, the licensee discovered

degradation of the baffle plates on the interior of the heat exchanger. On October 9, 2003, the

licensee formally documented their verbal request made on October 8, 2003, for discretionary

enforcement regarding Technical Specification (TS) 3.6.6, “Containment Spray System.” The

licensee requested to extend the allowed outage time an additional 336 hours from the

72 hours allowed by the TS to support the inspection, debris removal, repair activities, and

subsequent testing necessary to return the heat exchanger to service. The NRC staff verbally

agreed to the NOED on October 8, 2003, and documented the decision in a letter to the

licensee dated October 14, 2003. The licensee has established compensatory measures until

the heat exchanger can be returned to service. The NRC intends to exercise enforcement

discretion regarding the degraded 1B CSS heat exchanger from October 8 until

October 22, 2003.

Davis-Besse Nuclear Power Station Plant Status

The licensee completed its 7-day test at normal operating pressure (NOP) and no-load

operating temperature. Following cooldown, the licensee inspected the bottom reactor vessel

head and did not find any indication of reactor coolant system leakage.

The licensee removed the high pressure injection pumps and shipped them offsite for

modification. There is a public meeting scheduled for October 21, 2003, in Rockville, MD, to

discuss the pump modification.

Davis-Besse 0350 Oversight Panel public meetings were held on October 7, 2003, near the

site. At the afternoon meeting, the licensee discussed NOP test performance and its remaining

actions for restart. Introduced at the meeting was the new FirstEnergy Nuclear Operating

Company Senior Vice-President for Engineering and Support Services, Joe Hagan. Also, the
October 17, 2003 ENCLOSURE A

hiring of Barry Allen from Entergy to be Plant Manager was mentioned. He has experience in

engineering, maintenance, and emergency preparedness and is scheduled to arrive by the end

of October. The evening meeting was held with the public. The NRC Deputy Executive

Director for Reactor Programs attended both Oversight Panel meetings.

Issuance of Ginna and V. C. Summer License Renewal Safety Evaluation Reports with Open

Items

By letters dated July 30 and August 6, 2002, Rochester Gas and Electric Corporation and

South Carolina Electric and Gas Company submitted applications to renew the operating

licenses for the R. E. Ginna Nuclear Power Plant and Virgil C. Summer Nuclear Station. On

October 9, 2003, the staff issued its safety evaluation reports with open items for both plants. 

The staff plans to present the results of its evaluation to the Advisory Committee on Reactor

Safeguards on November 4 and December 3, 2003, for the Ginna and V. C. Summer reviews,

respectively.

License Renewal Application for Arkansas Nuclear One, Unit 2

On October 15, 2003, the staff received the Entergy Operations, Inc., license renewal

application for the Arkansas Nuclear One, Unit 2. Arkansas Nuclear One, Unit 2 is a

pressurized water reactor designed by Combustion Engineering with a current operating license

that expires on July 17, 2018. The staff plans to review this application using an improved

license renewal review process to enhance the effectiveness and efficiency of the staff review.

NRC Regulatory Issue Summary (RIS) 2003-16: NRC Threat Advisory and Protective

Measures System Dated October 7, 2003

The NRC previously issued guidance regarding the Homeland Security Advisory System

(HSAS) to certain groups of NRC licensees in a series of RISs issued in 2002-12A through -12I

and -12L. On October 7, 2003, the NRC issued RIS 2003-16 to identify a change in the

implementation of the HSAS for those who received these RISs, excluding panoramic

irradiators who received this change in RIS 2002-12L. The change is required by Homeland

Security Presidential Directive (HSPD)-5, “Management of Domestic Incidents,” dated

February 28, 2003. 

NRC Regulatory Issue Summary 2003-18: “Use of NEI 99-01, ‘Methodology for Development of

Emergency Action Levels,’ Revision 4, Dated January 2003,” Dated October 8, 2003

The NRC is issuing this regulatory issue summary (RIS) to inform addressees that the NRC has

reviewed Nuclear Energy Institute (NEI) 99-01 “Methodology for Development of Emergency

Action Levels,” Revision 4, January 2003, and is endorsing the report for use as guidance in

developing or changing a standard emergency classification and action level scheme. In

addition, this RIS provides recommendations to assist licensees in determining whether to seek

prior NRC approval of deviations from the new guidance. 
October 17, 2003 ENCLOSURE A

NRC Bulletin 2003-04: Rebaselining of Data In The Nuclear Materials Management and

Safeguards System, Dated October 8, 2003

NRC Bulletin 2003-04 was issued to notify licensees about performance concerns associated

with their reporting data to, and the resulting material balances contained in, the Nuclear

Materials Management and Safeguards System database. This bulletin requests affected

licensees to perform a one-time reporting of the quantities of special nuclear material and of

foreign obligated source material in their possession. 

NRC/NEI Standards and Recommend Practices for Establishing Setpoints for Nuclear SafetyRelated Instrumentation

On October 8, 2003, the staff from the Division of Inspection Program Management (DIPM)

chaired a public meeting with the Nuclear Energy Institute (NEI). Attending the meeting were

over 50 representatives from throughout the industry, including Instrumentations Systems and

Automation (ISA) Society committee members, multiple utilities, consultants, vendors, vendor

owners groups, and the media. The purpose of the meeting was to discuss the various aspects

regarding implementation of setpoint methodologies related to ISA 67.04, “Setpoints for Nuclear

Safety-related Instrumentation.” Nuclear instrumentation setpoints calculated using ISA 67.04

Part II, Method 3, may not be conservative for setting trip setpoints limits. The impacts of

potential nonconservative setpoint are not yet understood, but the staff believes licensees with

planned or pending power uprate applications in the 5% - 20% rated thermal power range and

licensees without an approved setpoint methodology are potentially impacted by any staff

clarification of acceptance criteria of ISA 67.04 Method 3. Industry estimates that one-third of

the operating licenses may be affected.

The staff continues to work with industry to ensure resolution of this issue is accomplished in a

timely manner. In this regard, the meeting concluded with agreement on a process to define

the issues and then proceed to work through any identified generic concerns to effect

appropriate changes in industry application of setpoint methodologies. The next NEI setpoint

meeting is scheduled for November 14, 2003. The purpose of the meeting is to identify

problems associated with implementation of ISA 67.04, Part II, Method 3. 

Completion of OMB PART for the Reactor Inspection and Performance Assessment program

The Office of Management and Budget (OMB) completed its review of the Reactor Inspection

and Performance Assessment Program using the Program Assessment Rating Tool (PART)

and scored the Program at 89%. This corresponds to an "Effective" rating by OMB for the

management of the Program, the highest rating possible under the PART system. Of the 234

Federal programs evaluated last year, only 6% of them received an "Effective" rating. The

PART is a program evaluation tool developed and implemented by OMB to evaluate the

management of all Federal programs in a manner that is consistent and objective. The Reactor

Inspection and Performance Assessment Program was the first NRR program evaluated by

using the PART process.
October 17, 2003 ENCLOSURE A

AP1000 Structural Audit

NRC staff conducted a structural audit of the AP1000 standard design at Monroeville, PA from

October 6 to October 9, 2003. The objective of this audit was to review design calculations

related to open issues from the Draft Safety Evaluation Report (DSER) of June 2003 in

Sections 2.5, 3.7, 3.8, 19.2.6, and 19A and Chapter 14, and to obtain additional information or

clarification to resolve as many issues as possible. These DSER sections deal with the seismic

analysis, structural design, and seismic margins issues. 

The audit team consisted of two Division of Engineering staff members, a Division of

Regulatory Improvement Programs staff member, and NRC consultants. Prior to the audit,

there were a total of 47 open issues in the structural and seismic area. As a result of the

focused and detailed review effort by the team, all but five open issues were closed, and a

resolution path on the remaining five open issues was achieved, based on verbal agreement on

options. Significant efficiencies in the AP1000 review effort was gained for the NRC as a result

of the audit. 

NRC Conference on Vessel Head Penetration (VHP) Inspection, Cracking and Repairs

During the week of September 29, the NRC’s Office of Nuclear Regulatory Research (RES)

sponsored an international conference on vessel head penetration inspection, cracking, and

repairs. The conference brought together industry leaders to describe and discuss international

experience with cracking of Alloy 600 components, regulatory approaches to ensure safety of

these components, and data on laboratory test of cracking of Alloy 600 base material used in

vessel head penetration nozzles along with Alloy 82/182 weld material. 

A representative from the Division of Engineering (DE) chaired a conference session and

provided a presentation entitled “U.S. Regulatory Experience and Prognosis with RPV [Reactor

Pressure Vessel] Head Degradation and VHP Nozzle Cracking.” DE’s senior level

management participated in a panel discussion with leaders from industry and RES that

concluded the conference.
October 17, 2003 ENCLOSURE B

Office of Nuclear Material Safety and Safeguards

Items of Interest

Week Ending October 17, 2003

Meeting with Gosatomnador (GAN)

On October 1-3, 2003, NRC staff from the Office of Nuclear Material Safety and Safeguards

and the Office of International Programs participated in a meeting with representatives of the

Department of Energy (DOE) and GAN. The purpose of the meeting was to discuss

radiological threat reduction and source control. GAN has requested support from DOE and

NRC in improving its regulatory program for control of radioactive sources. NRC staff plans to

provide support, funded by DOE, for some of these activities. The meeting was held to discuss

in detail the areas of possible assistance, and develop a path forward.

American National Standards Institute (ANSI) N43.7 Working Committee Meeting at NRC

On October 14-15, 2003, the Division of Industrial and Medical Nuclear Safety hosted the ANSI

Working Committee to develop the first major revision, since it was issued in 1977, to ANSI

Standard N43.7, “Safe Design and Use of Self-Contained, Dry-Source Storage Gamma

Irradiators (Category I).” In the meeting, 10 experts from the U.S. and Canada finalized a large

number of updates to the Standard, which included: (1) expanding the scope from gamma

only, to both gamma and beta sources; (2) introducing area monitoring and other radiation

protection measures; (3) differentiating the responsibilities of the manufacturers from those of

the operators; (4) addressing security measures; and (5) bringing the Standard into

conformance with the recently updated standard, N43.10, for Categories II and IV (wet storage)

irradiators. Before the end of 2003, the Committee intends to forward the finalized document to

ANSI for publication.

Management Meeting with Nuclear Fuel Services

To fulfill licensee commitments, on October 9, 2003, staff from the Office of Nuclear Material

Safety and Safeguards, the Office of Nuclear Security and Incident Response, and Region II

(RII) met with Nuclear Fuel Services (NFS) concerning root causes and corrective actions for

recent failures. Over the past year, NRC has identified issues related to the security program,

the material control and accountability program, and procedural compliance and management

oversight. NFS explained the actions it was taking to improve the safety culture at the facility. 

RII staff announced that it intends to increase inspection oversight by placing a second

Resident Inspector at the site. It was agreed that additional meetings will be scheduled in the

coming months to brief NRC management on progress at the facility.

Special Team Inspection at Honeywell Uranium Conversion Facility

On October 6-10, 2003, staff from the Office of Nuclear Material Safety and Safeguards

participated in a special team inspection, led by Region II, at the Honeywell International, Inc.,

uranium conversion facility in Metropolis, Illinois. The team was responding to the release of a

small amount of UF6 on September 30. This leak followed earlier releases of non-NRCregulated hazardous chemicals. The licensee currently has the NRC-regulated portion of the

facility shutdown and is reviewing and revising procedures throughout the site. Honeywell will
October 17, 2003 ENCLOSURE B

discuss its corrective actions with NRC before the NRC-regulated plant operations are

restarted.

Unsaturated Zone Interest Group 2003 Meeting

On October 8-10, 2003, staff from the Division of Waste Management attended the

Unsaturated Zone Interest Group 2003 Meeting in Richland, Washington. This biannual

meeting, hosted by the Pacific Northwest National Laboratory, provided a unique opportunity for

scientists to meet and share unsaturated zone research results. Topics discussed included:

(1) uncertainty and risk analysis related to radionuclide transport; (2) methods of estimating and

measuring flow and transport parameters; (3) methods and problems with upscaling

parameters from lab to field scale; (4) preferential flow paths and unsaturated aniosotropy; and

(5) fingering and hydrodynamic instability. The 2-day meeting was followed by a field trip to the

Hanford Site to view ongoing unsaturated zone research on radionuclide transport, and sites of

historical and scientific interest.

Meeting with Westinghouse Regarding Traveller Transport Package for Fresh Fuel Assemblies

On October 14, 2003, Spent Fuel Project Office staff met with Westinghouse Electric Company

to discuss the design of the Model No. Traveller package. The Traveller is being designed to

transport unirradiated pressurized-water reactor fuel assemblies. Westinghouse discussed

results of full-scale certification tests performed on the package and design changes that have

been incorporated as a result of the testing program. Westinghouse is planning to subject the

modified damaged package to a fire test. It plans to submit an application for package approval

to NRC in November 2003.
October 17, 2003 ENCLOSURE C

Office of Nuclear Regulatory Research

Items of Interest

Week Ending October 17, 2003

Presentation to Advisory Committee on Reactor Safety (ACRS) Subcommittee on Formal

Decision Methods

On October 10, 2003, RES staff presented to the ACRS Subcommittee on Reliability and

Probabilistic Risk Assessment recent work on formal decision making methods. ACRS

recommended that staff continue to aggressively pursue formal decision making in a wide

range of NRC activities and include them in training programs. In this way, common elements

that have contributed to the success of Agency programs, such as the Reactor Oversight

Process, could be communicated as part of the instructional material. ACRS members also

noted that RES work, which included NUREG/CR-6833, "Formal Methods of Decision Analysis

Applied to Prioritization of Research and Other Topics," could be used for other initiatives such

as knowledge preservation and management.

ACRS Subcommittee Briefing on Human Factors

On October 9, 2003, RES staff briefed the ACRS Subcommittee on Reliability, Probability Risk

Assessment, and Human Factors on human factors (HF) research. The first part of the briefing

focused on ongoing HF research activities and covered advanced reactors, the Halden Reactor

Project, risk communications guidelines, and general support that RES provides other NRC

offices. General support included both fatigue rulemaking and review of the MOX and gas

centrifuge facilities. The second half of the meeting focused on safety culture and associated

international activities, and included potential performance indicators in three areas: corrective

action program, safety conscious work environment, and human performance. The meeting

closed with ACRS Subcommittee members encouraging research that would support

development of human performance indicators and understanding its link to plant safety.

ACRS Briefing on the Standardized Plan Analysis Risk (SPAR) Human Reliability Analysis

Methodology

On October 9, 2003, RES staff made a presentation at the joint meeting of the ACRS

Probabilistic Risk Assessment (PRA) and Human Factors Subcommittees on the human

reliability analysis (HRA) methodology for the SPAR models. 

The presentation covered the technical aspects of the SPAR HRA methodology (SPAR-H

Method), the scope of applicability of the method, and the peer review process and results. The

Subcommittee members agreed that there is an agency need for a simplified HRA methodology

and that the SPAR-H method is technically sound when applied within its intended scope. The

Subcommittee members also made several suggestions to improve the user-friendliness of the

method and associated documentation.
October 17, 2003 ENCLOSURE C

ACRS Briefing on Risk-Based Analyses of Reactor Operating Experience

On October 10, 2003, RES staff made a presentation at the joint meeting of the ACRS

Subcommittee on Reliability and Probabilistic Risk Assessment on OERAB activities in the riskbased analysis of reactor operating experience. 

The staff discussed the following topics: (1) data collection and analysis, the Accident

Sequence Precursor (ASP) program, (2) the industry trends program, (3) the Standardized

Plant Analysis Risk (SPAR) model development program, and (4) the Mitigating Systems

Performance Index (MSPI). Subcommittee members indicated that these programs are useful

Agency initiatives and that much of the insights of the work performed (in particular, the

uncertainty analyses performed as part of the ASP program, and the lessons learned from the

MSPI pilot studies) could be useful in how PRA quality and technical adequacy can be defined.

ACRS Briefing on Low Power and Shutdown Risk

On October 10, 2003, RES staff made a presentation at the joint meeting of the ACRS PRA

and Human Factors Subcommittees on work related to low power and shutdown (LPSD) risk. 

Current LPSD risk work, including the revision of NUREG/CR-6595, “An Approach for

Estimating the Frequencies of Various Containment Failure Modes and Bypass Events,”

supports the American Nuclear Society (ANS) LPSD PRA standard development. This also

includes an assessment of the feasibility of extending the fire risk re-quantification from full to

LPSD operation and the development of LPSD risk insights in support of the worker fatigue

rulemaking effort. International activities involving the Cooperative PRA LPSD and the

Committee on the Safety of Nuclear Installations (CSNI) LPSD working groups were also

discussed. 

ACRS Briefing on Fire Risk Research

On October 10, 2003, RES staff made a presentation at the joint meeting of the ACRS PRA

and Human Factors Subcommittees on fire risk research. 

Fire risk research includes: (1) the revision of the fire protection Significance Determination

Process; (2) circuit analysis; (3) risk-informed, performance-based fire protection rulemaking

(e.g., endorsing the National Fire Protection Association (NFPA) standard 805); (4) the ANS full

power fire risk standard; and (5) fire barrier testing. The staff also discussed supporting

research programs in fire model benchmark and validation in methods, tools, and data (the joint

NRC/Electric Power Research Institute (EPRI) fire risk requantification studies), and related

work with international partners. The ACRS, in consideration of the fire protection rulemaking,

is interested in RES looking at the feasibility of developing guidance for conducting low power

and shutdown fire risk analysis.

ACRS Briefing on Human Reliability Analysis

On October 10, 2003, RES staff made a presentation at the joint meeting of the ACRS PRA

and Human Factors Subcommittees on the Human Reliability Analysis (HRA) Research

Program Plan.
October 17, 2003 ENCLOSURE C

The presentation included: (1) the status of the development of guidance for performing and

reviewing HRAs to be used as supplemental guidance to the American Society of Mechanical

Engineers (ASME) PRA standard; (2) the status of the development of a human performance

information repository (INFORM); and (3) the status of the feasibility study to identify HRA

needs for Materials and Waste. The Committee on the Safety of Nuclear Installations (CSNI)

working group efforts on developing a framework on HRA data sharing and the Halden

Program efforts on designing and performing simulator experiments for HRA were also

mentioned in the briefing. The ACRS subcommittee stated that both the HRA guidance and

INFORM are important activities and asked the staff to plan for a follow-up briefing by early next

year.

Agreement on the Second Phase of the Organization for Economic Cooperation and

Development (OECD) Masca Project: A Project to Investigate Chemical and Fission Product

Effects on the Thermal Loadings Imposed on the Reactor Vessel by a Convective Corium Pool

During a Severe Accident

On October 14, 2003, the EDO signed the international agreement between the USNRC and

the OECD relating to the OECD MASCA Project: “A Project to Investigate Chemical and

Fission Product Effects on the Thermal Loadings Imposed on the Reactor Vessel by a

Convective Corium Pool During a Severe Accident.” The Office of Nuclear Regulatory

Research forwarded this agreement to the OECD on October 15, 2003. This Agreement was

effective upon signature, and will remain in force until June 30, 2006. 

This Agreement defines the terms and conditions by which the USNRC and 13 additional

participating countries of the OECD will establish cooperation for the continuation of the

investigative work that was initiated in the first phase of the MASCA project, which produced

highly valuable results and enhanced our understanding of severe accidents under core melt

conditions. 

The second phase of the project is to further investigate the effects of the corium chemical

conditions and composition on melt stratification to understand the extent to which stratification

can lead to uneven thermal loading of the lower head of the reactor pressure vessel, and thus,

affect its integrity. This Agreement provides the framework for program management,

experimental testing to be conducted, and the parameters to be investigated in order to assess

the effects of corium chemistry conditions (e.g., fission product partitioning, corium vessel

interaction, etc.), and composition on melt stratification. Experimental data will be obtained on

thermal-physical properties for various high temperature molten core materials from differentscale corium tests. The data and insights gained from this project will enhance understanding

of in-vessel retention of molten corium, possible vessel failure location(s) and containment

challenges, and improve the severe analysis tool (e.g., MELCOR code) used for regulatory

analyses. 

Workshop on Modifications at Nuclear Power Plants - Operating Experience, Safety

Significance, and the Role of Human Factors and Organization

On October 6-9, 2003, RES and contractor staff (Brookhaven National Laboratory) attended a

Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI),

Working Group Operating Experience (WGOE) and Special Experts Group on Human and
October 17, 2003 ENCLOSURE C

Organizational Factors (SEGHOF) Workshop in cooperation with IRSN in Paris, France. The

general objective of the workshop was to bring experts together to exchange and disseminate

information about the safety aspects and role of human factors in nuclear power plant

modifications. International experience of events and modification processes were discussed

during the workshop and there was considerable sharing of good practices for both regulators

and licensees. Forty-five people, representing 13 countries (including International Atomic

Energy Agency (IAEA) and World Association of Nuclear Operators (WANO)), participated in

plenary and discussion sessions. The workshop results will be published in the near future and

will be used to steer international developments in the area of nuclear power plant modification

safety.

Coordination Meeting on Proactive Materials Degradation

On October 14, 2003, RES staff met with industry representatives from the Electric Power

Research Institute (EPRI), Nuclear Energy Institute (NEI), and Southern Nuclear Operating

Company who are instrumental in developing and carrying out the industry program on

materials degradation. The purpose of the meeting was to discuss NRC and industry

cooperation on methods and plans to identify locations for potential future materials

degradation of reactor components, and on research needed to proactively allow the prediction,

detection, evaluation, mitigation, and management of materials degradation. It was agreed by

all parties that there is substantial overlap of interests and plans between RES and industry and

that these efforts and activities should be undertaken cooperatively. 

Telecon with CNSC on Positive Power Coefficient in Maple 1 Startup Tests

On October 15, 2003, NRR and RES staff participated in a conference phone call with two staff

members of the Canadian Nuclear Safety Commission (CNSC) to seek technical information on

the recent unexpected measurement of positive power coefficients of reactivity during startup

testing of the new Maple 1 isotope production reactor. The staff is interested in the test results

because they could have broader implications on the expected accuracy of reactivity coefficient

predictions for existing and new reactor types of interest in the U.S., including ACR-700. CNSC

staff briefly described the Maple 1 reactor, and provided preliminary observations on the

predicted negative and measured positive power coefficients and on associated measurement

uncertainties. CNSC stated that the Maple 1 licensee, Atomic Energy of Canada Limited

(AECL), has committed to providing in November 2003 a detailed analysis, using state of-theart methods, of the Maple 1 power coefficient predictions and measurements. This analysis will

be publicly available. The staff is considering requesting AECL to provide information on this

analysis. 
October 17, 2003 ENCLOSURE D

Nuclear Security and Incident Response

Items of Interest

Week Ending October 17, 2003

Preliminary Notifications

1. PNO-IV-03-043, Sacred Heart Medical Center - POTENTIAL BRACHYTHERAPY

MISADMINISTRATION.

2. PNO-III-03-042, Wisconsin Public Service Corporation - POTENTIAL EXPOSURE TO

MEMBERS OF THE PUBLIC.
October 17, 2003 ENCLOSURE F

Office of Administration 

Items of Interest 

Week Ending October 17, 2003

Ion Technology; Receipt of Petition for Rulemaking (PRM-40-29)

A document requesting public comment on a petition for rulemaking filed by Terrence O. Hee,

Ion Technology, was published in the Federal Register on October 15, 2003 (68 FR 59346). 

The petitioner requests that the NRC amend its regulations regarding unimportant quantities of

source material (10 CFR 40.13(c)) to exempt end users of a catalytic device containing thorium

from NRC’s licensing requirements. The petitioner asserts that this device, in conjunction with

a patented new methodology, could substantially reduce air pollution chemicals from mobile

and stationary combustion processes. The comment period for this action closes

December 29, 2003.

The companion proposed rule to this direct final rule was published in the Federal Register on

October 7, 2003 (68 FR 57839 ). The comment period closes November 6, 2003.

Electronic Maintenance and Submission of Information (AH33 - 10 CFR Chapter I)

On October 10, 2003, a final rule was published amending NRC’s regulations to clarify when

and how licensees and other members of the public may use electronic means to communicate

with the agency (68 FR 58792). The amendments are necessary to implement the Government

Paperwork Elimination Act. The NRC is also updating its guidance on how to submit

documents to the agency electronically. The final rule becomes effective January 1, 2004.
October 17, 2003 ENCLOSURE G

Chief Information Officer

Items of Interest

Week Ending October 17, 2003

Agency’s Software Maintenance and Operational Support for Applications Systems and

Environment Contract is Awarded

On September 26, 2003, the agency's software maintenance and operational support for

applications systems and environment contract was awarded to OAO Corporation (OAO). OAO

is a wholly-owned subsidiary of Lockheed Martin and is also the incumbent contractor providing

these services to NRC. The new contract is performance-based, and has a 2-year base-period

with two 1-year options. The 2-year base period begins October 18, 2003, to coincide with the

end of the current contract on October 17, 2003.

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

October 10 through October 16, 2003:

Reactor License No. R-98, transfer from Aerotest, all documents FOIA/PA-2004-0008

Radiological Survey, 12-6-96, prepared by ATG Inc., on 464 Ellis

Street and 447 N. Whisman Road, Mt. View, CA

FOIA/PA-2004-0009

Three Mile Island, documents relating to 1979 accident FOIA/PA-2004-0010

IG Report 02-381 FOIA/PA-2004-0011

MB Associates, named individuals, all documents; references to

gyrojet(s)

FOIA/PA-2004-0012

Communications, complaints, investigations between NRC and

Wesley K. Clark, positions held, 1975 to present

FOIA/PA-2004-0013

MLTS, active and retired facilities FOIA/PA-2004-0014

Allegation RIV-96-A-0285 including all correspondence between

named individual & NRC

FOIA/PA-2004-0015

Docket No. 40-8681, Standby Trust Agreement, 4-29-97 FOIA/PA-2004-0016

Three Mile Island Plant, causes of partial meltdown, 3-28-79, all

records

FOIA/PA-2004-0017
October 17, 2003 ENCLOSURE I

Office of Human Resources

Items of Interest

Week Ending October 17, 2003

Arrivals

DIEDERICH, Karl REACTOR INSPECTOR R-I

DONALDSON, Leslie SR. PROGRAM ANALYST OCFO

FORD, Anne SECRETARY (OA) R-I

FRATO, Martin PHYSICAL SECURITY SPECIALIST R-IV

GLAROS, Rachel CONTRACT SPECIALIST ADM

GUARRO, Sergio CONSULTANT ACRS

JACOX, Christine SECRETARY (OA) OCFO

REESER, David REACTOR ENGINEER R-III

THOMPSON, Elizabeth HEALTH PHYSICIST NMSS

Departures

BUSSARD, Victoria SECRETARY(OA) HR
October 17, 2003 ENCLOSURE M

Office of Public Affairs

Items of Interest

Week Ending October 17, 2003

Media Interest

FirstEnergy officials predict the troubled Davis-Besse plant in Ohio will be ready to resume

operations in November. Representative Kucinich has asked NRC to reconsider his petition to

revoke Davis-Besse’s operating license.

The transport of two decommissioned reactor vessels to a low-level waste disposal site at

Barnwell, SC, from Big Rock in Michigan (transport underway) and from San Onofre in

California (shipment around the tip of South America expected to begin soon).

Press Releases

Headquarters:

03-133 NRC Announces Availability of Application for Early Site Permit at Clinton

Nuclear Plant Location (10/15)

Regions:

I-03-062 NRC, Company to Discuss License Renewal Inspection of Ginna Plant

(10/15)

II-03-047 NRC Names Hagar Senior Resident Inspector at Robinson Nuclear Plant

(10/16)

IV-03-040 NRC Assigns New Resident Inspector to Arkansas Nuclear One (10/14)

IV-03-041 NRC Proposes $90,000 Fine for Schlumberger Technology Corp. (10/16)
October 17, 2003 ENCLOSURE O

Office of the Secretary

Items of Interest

Week Ending October 17, 2003

Document Released

to Public

Date Subject

Decision Documents

1. SECY-03-0172 10/6/03 Reimbursement of the Travel Expenses of

Individuals Requested to Attend a

Predecisional Enforcement Conference

SRM on 03-0172 10/15/03 (same)

Commission Voting

Record on 03-0172

10/15/03 (same)

2. COMSECY-03-0046 9/30/03 Potential Agreement State Policy Issues

From an NRC Response to a Citizen’s

Questions

SRM on 03-0046 10/15/03 (same)

Commission Voting

Record on 03-0046

10/15/03 (same)

Information Papers

1. SECY-03-0174 10/10/03 SECY-03-0174 Weekly Information Report -

Week Ending October 3, 2003

2. SECY-03-0176 10/16/03 SECY-03-0176 Weekly Information Report -

Week Ending October 10, 2003

Memoranda

1. M031015A 10/15/03 Staff Requirements - Affirmation Session: I.

SECY-03-0170 - Pacific Gas & Electric Co.

(Diablo Canyon Power Plant Independent

Spent Fuel Storage Installation); Petitions

for Review of LBP-02-23 and LBP-03-11

Federal Register Notices Issued

1. Advisory Committee on Nuclear Waste Notice of Meeting (146th).

2. Advisory Committee on Nuclear Waste Meeting on Planning and Procedures.

3. Notice of Receipt of Rulemaking - Terrence O. Hee, Ion Technology.
October 17, 2003 ENCLOSURE O

4. Procedures for Advisory Committee on Reactor Safeguards Meetings.

5. Procedures for Advisory Committee on Nuclear Waste Meetings.

6. Advisory Committee on Reactor Safeguards Subcommittee Meeting on Safeguards and

Security.

7. Advisory Committee on Reactor Safeguards Subcommittee Meeting on Planning and

Procedures.

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

License Renewal.
October 17, 2003 ENCLOSURE P

Region II

Items of Interest

Week Ending October 17, 2003

Florida Power Corporation - Crystal River Nuclear Plant

On October 16, 2003, the Regional Administrator toured the Crystal River Nuclear Plant, in

Crystal River, FL, and observed the installation activities for the reactor vessel head

replacement.

Virginia Electric and Power Company - Commissioner Merrifield Visits the Surry Nuclear Plant

On October 15, 2003, Commissioner Merrifield, accompanied by the Director, Division of

Reactor Projects, toured the Surry Nuclear Power Plant in Surry, VA and met with licensee

management.

United States Enrichment Corporation, Paducah and Portsmouth Gaseous Diffusion Plants

On October 14, 2003, representatives from United States Enrichment Corporation, Paducah

and Portsmouth Gaseous Diffusion Plants, attended a management meeting in the Regional

Office. The purpose of this meeting was to discuss their safety conscious work environment

program.

Response Technical Manual Training

On October 15-16, 2003, the Response Technical Manual Training was presented to selected

staff members in the Regional office by a representative from the Office of Nuclear Security and

Incident Response. 
October 17, 2003 ENCLOSURE P

Region IV

Items of Interest

Week Ending October 17, 2003

Yucca Mountain

On October 15, 2003, the Regional Administrator accompanied the Director of the Office of

Nuclear Material Safety and Safeguards, the Chief Financial Officer, Commissioner Julio

Barcelo Vesnet of the Spanish Nuclear Regulatory Commission, and other Office of Nuclear

Material Safety and Safeguards and Office of International Programs representatives on a tour

of the Yucca Mountain site in Nevada. The tour included a general discussion with the NRC,

onsite representatives, and representatives of the Department of Energy. 

Schlumberger Technology Corporation

On October 14, Region IV issued escalated enforcement, including a proposed a fine of

$90,000 to Schlumberger Technology Corp. (STC) of Sugar Land, Texas, for violations of NRC

radioactive material handling regulations. The violation stemmed from a May 2002 incident in

which 13 oilfield workers received exposures in excess of NRC’s annual limits for members of

the public. NRC also issued Notices of Violation to two former STC employees who deliberately

failed to conduct radiation surveys following well-logging activities, resulting in loss of control of

a Cs-137 well-logging source and the exposures of the oilfield workers.
October 17, 2003 

Office of Congressional Affairs

Items of Interest

Week Ending October 17, 2003

CONGRESSIONAL HEARING SCHEDULE, NO. 35

OCA

Contact

DATE

&

PLACE

TIME WITNESS SUBJECT 

Combs TBA

2123 RHOB

TBA NRC, DOE, Bechtel, NEI,

NARUC

Review of the Progress of DOE’sYucca Mountain Project

Reps. BaEnergy aEnergy a

Gerke 10/22/03

SD-342

10:30 Markup S. 129, Federal Workforce

Flexibility Act; H.R. 3159,Government Network Security Act

Senators Governm

Gerke 10/29/03

2154 RHOB

 2:30 GAO, AMS, and others Government Financial

Management Problems

Reps. DaGovernm