INFORMATION REPORT

July 24, 2002 SECY-02-0141For: The Commissioners

From: John W. Craig, Assistant for Operations, Office of the EDO

Subject: SECY-02-0141 WEEKLY INFORMATION REPORT - WEEK 

ENDING JULY 19, 2002

Contents Enclosure

Nuclear Reactor Regulation ANuclear Material Safety and Safeguards BNuclear Regulatory Research CNuclear Security and Incident Response DGeneral Counsel E*Administration FChief Information Officer G*Chief Financial Officer H*Human Resources ISmall Business & Civil Rights J*Enforcement K*State and Tribal Programs L*Public Affairs MInternational Programs NOffice of the Secretary ORegion I P*Region II PRegion III PRegion IV P*Executive Director for Operations Q*Congressional Affairs R*No input this week.

 /RA/

John W. CraigAssistant for Operations, OEDO

Contact:M. Layton, OEDO
July 24, 2002 SECY-02-0141 

For: The Commissioners

From: John W. Craig, Assistant for Operations, Office of the EDO

Subject: SECY-02-0141 WEEKLY INFORMATION REPORT - WEEK 

ENDING JULY 19, 2002

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.

John W. Craig

Assistant for Operations, OEDO

Contact:

M. Layton, OEDO

DISTRIBUTION:

Central File

Public Document Name: C:\WIR\WEEK719.

ADAMS Accession Number: ML022060310

*Please see previous concurrence.

OEDO AO/OEDO

MLayton* JWCraig*

 7/24/02 7/2402
July 24, 2002 ENCLOSURE A

Office of Nuclear Reactor Regulation

Items of Interest

Week Ending July 19, 2002

Browns Ferry Units 2 & 3 Power Uprate

On July 10, 2002, the NRC staff met with representatives of the Tennessee Valley Authority

(TVA), licensee for Browns Ferry, and the General Electric Company (GE) concerning the

proposed extended power uprate for Browns Ferry Units 2 & 3. This would be the first

application based on the GE Constant Pressure Power Uprate (CPPU) Licensing Topical

Report. During the meeting, it became apparent that there were a number of issues that would

require interactions with TVA. 

Pilgrim Power Uprate Request

By letter dated July 5, 2002, Entergy Nuclear Operations, Inc. submitted an application for a

1.5% power uprate for the Pilgrim Nuclear Power Station. The licensee’s evaluation supporting

the request was performed in accordance with the guidance in NRC Regulatory Issue Summary

2002-03. The request was based on the Appendix K measurement uncertainty recovery and

involves a propose increase in the licensed power level from 1998 MWt to 2028 MWt. The

licensee plans to implement the power uprate following its refueling outage in mid-May 2003.

The licensee requested to meet with the staff to provide a presentation on the seismic analysis

portion of their power uprate submittal regarding the safety-relief valve down comers. The

meeting is scheduled for Wednesday, July 24, 2002.

Power Uprate Commission Briefing

On July 10, 2002, the staff briefed the Commission on the status of the power uprate program. 

The briefing covered approved, pending, and expected power uprate applications and the

contribution of these to the nation’s electrical generating capacity. The staff stated that

81 power uprates have been approved, 12 are under review, and 35 more are expected over

the next 5 years. The staff also noted that power uprates have safely added about 3800 MWe

to the nation’s electric generating capacity. The staff indicated that power uprates have been

assigned a high priority, are considered among the most significant licensing actions, and are

being reviewed in a manner that does not unnecessarily delay their completion.

The staff covered completed initiatives to improve the power uprate review process. The staff

reported that it has launched a power uprate web site, conducted a power uprate session at the

regulatory information conference, and conducted two public workshops related to power

uprates. The staff also noted that it has issued a regulatory issue summary to provide guidance

to licensees on the content of measurement uncertainty, recapture power uprate applications,

and improved predictability of schedules by enhancing management oversight of power uprate

reviews. The staff also discussed ongoing initiatives in the power uprate area including the

development of a review standard for extended power uprates. 
July 24, 2002 ENCLOSURE A

Public Meeting to Discuss Draft Regulatory Guidance on Control Room Habitability

On July 11, 2002, members of the Probabilistic Safety Assessment Branch (SPSB) hosted a

public meeting in King of Prussia, Pennsylvania (NRC Region I) to discuss draft regulatory

guidance on control room habitability. Similar meetings, in locations near the other NRC

Regional Offices, are scheduled to take place over the next couple of weeks. The intent of

these meetings is to solicit feedback from NRC stakeholders regarding the draft generic letter

and regulatory guidance on control room habitability issues. The following key technical issues

were discussed at the July 11 meeting: (1) establishment of technical specifications, (2) control

room testing methods and test frequency, (3) design bases; and (4) impact of smoke and fire

on control room habitability. Staff reported that during the meeting, approaches to resolving

differences among stakeholders on all of these issues were identified which appear to have a

wide level of support among stakeholders. 

NEI 00-04 Guidance Document

The staff met with Nuclear Energy Institute (NEI) July 10, 2002, to discuss their guidance

document (NEI 00-04, Draft Revision C, "10 CFR 50.69 SSC Categorization Guideline") related

to the categorization of structures, systems, and components (SSCs) under Option 2 (10 CFR

50.69). The interaction was productive in clarifying the intent of various portions of this

guidance and in focusing on remaining issues. The exchange will support the development of a

draft regulatory guide that will identify the necessary exceptions and enhancements to NEI 00-

04 to support the Option 2 rulemaking.

Visit to Steam Generator and Reactor Vessel Head Manufacturing Facility

On July 9-10, 2002, three staff from the Office of Nuclear Reactor Regulation visited B&W

Canada to meet with Duke Power and B&W Canada manufacturing personnel to discuss and

observe various aspects of the manufacture of once through and U-tube steam generators and

reactor vessel heads. Two personnel from RES (one of them a contractor) and two Region 2

inspectors also participated. Steam generators were in various stages of production and staff

had the opportunity to climb into them and gain a better understanding of their assembly and

internal features and some of the new design features. Similarly, for the reactor vessel heads,

the staff observed them in various stages of production. Of particular interest were the new

design of the J-groove and the in-process development of an improved machine welding

process to make the J-groove welds. The vessel head penetrations were also observed in

various stages of fabrication. Discussions included actions being taken to minimize residual

stresses from the welding process.

Seventh NRC/ASME Symposium on Valve and Pump Testing

The NRC and The American Society of Mechanical Engineers (ASME) jointly held the seventh

symposium on valve and pump testing at the Renaissance hotel in Washington, DC on July

16-18, 2002. The symposium is held every two years to provide for the exchange of

information on technical, programmatic, and regulatory issues related to the inservice testing of

safety-related pumps and valves in U.S. nuclear power plants. This year, the keynote speakers

included NRC Chairman Richard A. Meserve and ASME International President Susan H.

Skemp. The conference was well-attended with approximately 250 people from various utilities,
July 24, 2002 ENCLOSURE A

vendors, manufacturers, consulting companies, and regulatory agencies including

representatives from 10 foreign countries. There was considerable interest in the risk-informed

activities affecting inservice testing of pumps and valves.

Senior Management Meeting with Nuclear Energy Institute

On July 15, 2002, representatives from the Nuclear Energy Institute (NEI) met with NRC staff

and management. The meeting was requested by NEI as a follow-up to an April 1, 2002,

meeting and is the second of several periodic meetings between industry and NRC senior

management to discuss issues related to new reactor licensing. The main topics of this

meeting were: scheduling of new plant activities, status of Early Site Permit (ESP) activities,

Part 52 process issues, issues related to inspections, tests, analyses, and acceptance criteria

(ITAAC), and modular plant issues. Representatives from Dominion, Exelon and Entergy were

in attendance. NEI provided a status update to the list of issues related to ESPs. Other

discussions during the meeting included:

1. ITAAC implementation including the right level of detail for the ITAAC signoffs and the

staff’s proposal regarding Section 52.99 (new 52.229(e)) 

2. bounding plant parameter envelope (PPE) concept in ESP applications

3. use of a dedicated team approach to conduct the environmental, site safety and

emergency preparedness reviews associated with the three ESP applications scheduled

to be filed in June and September of 2003

Early Site Permits (ESP) Meeting

On July 16, 2002, representatives from NEI met with the NRC staff to discuss issues related to

Early Site Permits (ESP) applications and reviews. Representatives from Dominion, Exelon

and Entergy were in attendance. In addition to addressing follow-up from the June 13, 2002,

ESP meeting, the staff gave a presentation on the purpose and scope of the proposed staff

pre-application environmental site visit. The ESP applicants agreed to conduct a seismic and

geotechnical demonstration later this year in response to staff’s concerns regarding the

implementation of their seismic evaluation methodology. Industry presented the use of the

bounding Plant Parameter Envelope (PPE) approach to meet 10 CFR 52.17 requirements. 

Both staff and NEI agreed that additional dialogue was necessary before the staff could

determine whether the bounding PPE approach could satisfy the requirements. This topic and

the use of existing information will be on the August meeting agenda. 
July 24, 2002 ENCLOSURE A

Pre-application Review of the Westinghouse’s IRIS Design

In a July 11, 2002, letter Westinghouse requested a pre-application review of their International

Reactor Innovative and Secure (IRIS) design. IRIS is a small (100-300MWe) pressurized water

reactor design, featuring an integrated primary system – that is, all primary system

components, including the steam generators, coolant pumps and pressurizer are housed along

with the nuclear fuel in a single, large pressure vessel. In its request, Westinghouse proposes

IRIS pre-application interactions with the staff starting in September of 2002 going through June

of 2003. The letter further indicates a possible additional phase for a pre-application review and

submittal of a formal design certification in 2004 or 2005 when the AP1000 design certification

is completed.

NRC Information Notice 2002-02, Supplement 1: Recent Experience with Plugged Steam

Generator Tubes dated July 17, 2002

The U.S. Nuclear Regulatory Commission is issuing this information notice to inform

addressees of findings from recent inspections and examinations of steam generator tubes at

Oconee Nuclear Station Unit 1. The NRC anticipates that recipients will review the information

for applicability to their facilities and consider taking actions, as appropriate, to avoid similar

problems. 
July 24, 2002 ENCLOSURE B

Office of Nuclear Material Safety and Safeguards

Items of Interest

Week Ending July 19, 2002

Nuclear Energy Institute - Health Physics Forum

On July 15, 2002, Office of Nuclear Material Safety and Safeguards management presented

the current status of activities on control of solid material, at the Nuclear Energy Institute Health

Physics Forum in Clearwater, Florida. The presentation included a historical summary of

activities, the overarching findings and recommendations of the National Academy of Sciences

study, the status of technical basis work, and the status of international activities.

Meeting with Department of Energy on Yucca Mountain Criticality Issue

On July 9-10, 2002, staff from the Division of Waste Management met with Department of

Energy (DOE) Office of Civilian Radioactive Waste Management and their contractors, using

the Appendix 7 meeting format, to discuss the changes to the Disposal Criticality Analysis

Methodology Topical Report (Topical Report), Revision 01, which the Nuclear Regulatory

Commission (NRC) staff is currently reviewing. Since issuance of Revision 01 and the staff’s

detailed technical review, DOE has made additional changes to the overall methodology and

the probability model. During the meeting on July 9-10, DOE and its contractors presented their

changes and described their revised approaches. The staff also met with DOE and its

contractors at NRC's On-site Representatives’ office, to go over DOE's current efforts and draft

documents, that are under development, related to Yucca Mountain disposal criticality. As a

result, DOE agreed to send NRC a letter that lists the changes to the Topical Report, Revision

01, in about 2 weeks. Based on this letter, the staff will revise its schedule for the detailed

technical review of the Topical Report. In 2 to 3 months, DOE will submit the actual changes, to

the Topical Report, that will form the basis for issuance of an amendment to NRC’s Safety

Evaluation Report issued in June 2000.

Staff Attends Quarterly Interagency Committee on Dam Safety Meeting

On July 10, 2002, a member of the Division of Waste Management staff, who serves as the

Nuclear Regulatory Commission's Dam Safety Officer, attended the quarterly Interagency

Committee on Dam Safety (ICODS). The meeting took place at the Federal Emergency

Management Agency in Washington, DC. Highlights of the meeting included presentations

from the Task Force on Dam Safety Security, and an update from the Chair on the status of the

proposed Department of Homeland Security. The Nuclear Regulatory Commission is a

permanent member of ICODS, as a result of the Agency’s inspection responsibilities for safetyrelated and mill tailings dams at 14 sites. The Dam Safety Program is managed in accordance

with the Federal Guidelines for Dam Safety.

Staff Receives Revised Mixed-Oxide Fuel-Fabrication Facility Environmental Report

On July 11, 2002, Duke Cogema Stone & Webster submitted its revised Mixed-Oxide (MOX)

Fuel-Fabrication Facility Environmental Report (ER) to the Office of Nuclear Material Safety and

Safeguards staff. This revision to the MOX ER addresses changes in the Department of

Energy’s (DOE’s) plutonium disposition program announced by DOE during a meeting with the
July 24, 2002 ENCLOSURE B

staff on February 13, 2002. The changes include elimination of the plutonium immobilization

facility, processing changes in the MOX facility to remove impurities, and the addition of a new

waste-processing facility. Staff will complete its acceptance review of the document by

August 12, 2002, and intends to have meetings with the public in September 2002 to discuss

the changes. The draft Environmental Impact Statement is scheduled to be completed in

April 2003.

Public meeting on High-Burnup Fuel Issue

On July 10, 2002, representatives from the Spent Fuel Project Office, the Office of Nuclear

Regulatory Research, the Nuclear Energy Institute (NEI), the Electric Power Research Institute

(EPRI), and industry attended a meeting to discuss NEI/EPRI’s feedback on a Nuclear

Regulatory Commission (NRC) request for additional information dated April 17, 2002, related

to the issue of high-burnup fuel. NRC staff agreed to consider the information provided by

NEI/EPRI in the development of a forthcoming Interim Staff Guidance document dealing with

the topic of high-burnup fuel.

Issuance of Amendment to the Transnuclear, Inc., NUHOMS® MP-187 Multi-Purpose Spent

Fuel Cask Transportation Certificate of Compliance

On July 10, 2002, the Nuclear Regulatory Commission issued an amendment to the

NUHOMS® MP-187 Cask Transportation Certificate of Compliance (71-9255). The

amendment allowed for alternate design options to the Dry Shielded Canister (DSC)

components. Most of the changes were initiated to improve fabrication of the DSCs. The most

significant change was the addition of an alternate basket material for the failed fuel type DSC. 

This action was to support fuel loading operations at the Rancho Seco Independent Spent Fuel

Storage Installation.

Meeting with Portland General Electric Company to Discuss the Trojan Independent Spent Fuel

Storage Installation License Amendment Application

On July 10, 2002, Spent Fuel Project Office staff met with Portland General Electric (PGE) and

Holtec International in support of an amendment to the 10 CFR Part 72 license for the Trojan

Independent Spent Fuel Storage Installation. PGE discussed its proposed responses to the

staff’s Request for Additional Information (RAI). PGE’s responses to the staff’s RAIs are

scheduled to be submitted on July 29, 2002. The original amendment request was submitted in

October 2001. The final staff safety evaluation report and amended license are planned for

issuance in October 2002.

Issuance of Transnuclear, Inc., NUHOMS® MP-197 Multi-Purpose Spent Fuel Cask 

Transportation Packaging Certificate of Compliance

On July 12, 2002, the Nuclear Regulatory Commission issued Certificate of Compliance

(71-9302) for the NUHOMS® MP-197 Multi-Purpose spent fuel transportation cask. The

MP-197 Transport Cask is to be used for off-site transportation of NUHOMS® -61BT Dry

Shielded Canisters loaded with BWR fuel assemblies. The maximum heat load of the cask

is 15.9 kW.
July 24, 2002 ENCLOSURE B

Responses Received from Westinghouse Electric Company and Framatome, ANP, on

Confirmatory Action Letters on the performance of drum-type transportation packages

The Nuclear Regulatory Commission (NRC) received the initial response from Westinghouse

Electric Company and Framatome, ANP, Confirmatory Action Letters (CALs). The CALs were

issued because of potential problems related to performance of certain drum-type

transportation packages when subjected to the Hypothetical Accident Conditions 9-meter

(30-foot) drop test described in 10 CFR 71.73. Both responses contained sufficient justification

for continued use of the packages and a commitment to respond to all the requested items in

the CAL. NRC staff reviewed the justifications for continued use of the packages and found

them to be acceptable. The next step in the CAL is the development of test plans for retesting

the modified packages.
July 24, 2002 ENCLOSURE C

Office of Nuclear Regulatory Research

Items of Interest

Week Ending July 19, 2002

Assessment of Russian Capabilities re GT-MHR

During the second week of July, a 15 member team of representatives from U.S. government

and industry organizations visited Russia to assess Russian design and technical capabilities

that would be needed to build a Gas Turbine- Modular Helium Reactor (GT-MHR). An NRC

representative from the Office of Nuclear Regulatory Research (RES) attended the meeting as

an observer. The Russians plan to use the GT-MHR as a means to dispose of Russian

plutonium. Currently, the NRC is about to begin the pre-application review of General Atomics

(GA) GT-MHR. GA plans to capitalize on the Russian experience to support their preapplication review and follow-on design certification. The team visiting Russia consisted of

representatives from the Department of Energy, Idaho National Engineering and Environmental

Laboratory, Dominion Company, Entergy Company, Utility Advisory Board for the GT-MHR, and

attorneys from the firm of Shaw Pitman. In addition, the GT-MHR is competiting with another

approach that would burn MOX fuel in LWRs, as a means to reducing the plutonium stockpile in

Russia. The original schedule to build a GT-MHR prototype in Russia has now slipped about 2

years. It is estimated that the prototype will not be operational until 2007.
July 24, 2002 ENCLOSURE D

Nuclear Security and Incident Response

Items of Interest

Week Ending July 19, 2002

ICMs for Independent Spent Fuel Storage

On Thursday July 18, 2002, staff from the Office of Nuclear Security and Incident Response

and the Office of Nuclear Material Safety and Safeguards met with the Nuclear Energy Institute

(NEI), licensees, and States to further discuss the interim compensatory measures (ICMs) for

independent spent fuel storage installations. Fundamental differences between the NRC and

the industry positions were addressed. 

NSIR and Industry Hold Workshop on Expanded Table-top Drills

A closed meeting was held between NRC and industry representatives on July 12, 2002 to

discuss the expanded table-top drills that will be held between July and October of 2002. The

expanded table-top drills will evaluate the effectiveness of the interim compensatory measures

(ICMs) and the impact of the expanded adversary characteristics. The objective of the drills will

be to produce lessons learned, not graded evaluations of the performance of specific sites. 

There will be no "pass" or "fail" evaluations. The intent is to use the same series of drills at

each site. The summary of lessons learned will be a blind report. No site specific reports are

planned, unless the licensee requests such a report. In addition, part of the process will be to

determine how the off-site resources are integrated into the drill plans. It is expected that a

limited number of local law enforcement and State representatives will participate. 

NSIR and the US Coast Guard Hold Meeting on Protocols for Establishing Security Zones

Around Nuclear Power Plant Sites

A closed meeting was held on July 17, 2002, among staff from the Offices of Nuclear Security

and Incident Response, Office of Nuclear Reactor Regulation and the Office of the General

Counsel, with a representative from the U.S. Coast Guard (USCG) to discuss difficulties that

NRC licensees have experienced in their attempts to establish security zones around their sites

as required by the February 25, 2002 USCG Order. The purpose of the meeting was for the

NRC staff to gain a better understanding of the difficulties in establishing “demarcation” zones

around licensed sites. It was noted that the difficulties encountered appear to be isolated to a

single district (5 sites are affected thus far).

Top Officials (TOPOFF) 2 Seminar

The Division of Incident Response Operations staff, joined the Office of Public Affairs (OPA), 

and attended the first Top Officials (TOPOFF) 2 Seminar on July 17 and 18, 2002, in McLean,

Virginia. This seminar was devoted to "Public Communications During a Weapons of Mass

Destruction Incident" and NRC's participation was led by the Director of OPA. This two day

seminar was the first of six training events of the TOPOFF 2 exercise series leading up to a

joint United States and Canada government-wide counter-terrorism exercise in May, 2003. 

Other seminar attendees included representatives from eight Federal agencies, (including the

Office of Homeland Security), the States of Washington and Illinois, cities of Seattle and

Chicago and surrounding counties, the Government of Canada, and "subject matter experts"
July 24, 2002 ENCLOSURE D

from academia and the national news networks. A TOPOFF 2 seminar on Radioactive

Dispersal Devices (RDD) is scheduled for October 15 and 16, 2002. 

Preliminary Notifications

1. PNO-IV-02-36, Syncor Pharmacy, STOLEN VEHICLE CONTAINING RADIO

PHARMACEUTICALS.
July 24, 2002 ENCLOSURE F

Office of Administration 

Items of Interest 

Week Ending July 19, 2002

List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision; Withdrawal of Direct

Final Rule (Part 72)

A final rule that revises the HI-STORM 100 cask system listing in the list of approved spent fuel

storage casks was published in the Federal Register on July 15, 2002 (67 FR 46369). Among

other changes, the amendment adds new multipurpose canisters, containers for damaged fuel,

and high-seismic anchored overpacks; allows the storage of high-burnup fuel; and revises

selected thermal analysis tools. The final rule became effective July 15, 2002. 
July 24, 2002 ENCLOSURE G

Office of Human Resources

Items of Interest

Week Ending July 19, 2002

Arrivals

GIBBS, Russell* SENIOR REACTOR ANALYST NRR

KLEIN, Veronica NUCLEAR SAFETY INTERN NRR

MAS-PENARANDA, Delza NUCLEAR SAFETY INTERN RII

UNIKEWICZ, Steven MECHANICAL ENGINEER NRR

Retirements

None

Departures

None

*Transferred from RII effective 07/15/02
July 24, 2002 ENCLOSURE J

Week Ending July 19, 2002

Media Interest

There was media interest in two public meetings held in Oak Harbor, Ohio, regarding the

damaged reactor vessel head and its replacement at the Davis-Besse nuclear plant.

There was media interest in the future of the proposed Private Fuel Storage facility in Skull

Valley, Utah, following the Senate’s vote last week endorsing Yucca Mountain as a permanent

waste repository site.

Press Releases

Headquarters:

02-082 NRC Announces the Availability of License Renewal Application

for H.B. Robinson Nuclear Plant, Unit 2

02-083 NRC Seeks Public Comment on Proposed Rule For Spent Fuel

Storage

Regions:

I-02-047 NRC to Hold Public Meetings Regarding Draft Environmental

Impact Statement for Peach Bottom License Renewal Application 

I-02-048 William Raymond Named NRC Senior Resident Inspector at

Pilgrim Nuclear Power Plant

III-02-043 NRC Cites Point Beach Nuclear Plant for Violation Of "High

Importance to Safety"
July 24, 2002 ENCLOSURE N

Office of International Programs

Items of Interest

Week Ending July 19, 2002

Japanese Visit

On July 19, 2002, Mr. Takashi Suzuki, Director for International Nuclear Energy Affairs, Nuclear

and Industrial Safety Agency, METI, Japan, visited NRC and met with staff for an overview

briefing on NRC. Mr. Suzuki is visiting Washington as a participant in the International Visitors

Program sponsored by the State Department.
July 24, 2002 ENCLOSURE O

Office of the Secretary

Items of Interest

Week Ending July 19, 2002

Document Released

to Public

Date Subject

Decision Documents

Negative Consent Documents

Information Papers

1. SECY-02-0126 7/11/02 SECY-02-0126 Weekly Information Report -

Week Ending July 5, 2002

Memoranda

1. M0207010A 7/15/02 Staff Requirements - Briefing on License

Renewal Program and Power Uprate

Review Activities

2. M020710C 7/17/02 Meeting with Advisory Committee on

Reactor Safeguards (ACRS)

Commission Correspondence

1. Letter to Sandra R. Galef, New York State Assembly, dated July 12, 2002, responds to

request that the NRC require Entergy Nuclear Northeast to start immediately the process

of strengthening the spent fuel storage buildings at the Indian Point Energy Center. 
July 24, 2002 ENCLOSURE O

2. Letter to Representative Markey dated July 10, 2002 provides response to questions

about the status of a Pakistani man arrested in September 2001 on suspicion of

gathering information about the Salem and Hope Creek Nuclear Power Stations. 

3. Letter to Marilyn Kray, Exelon Generation, dated July 8, 2002, acknowledges receipt of

comments on SECY-02-0067, “Inspections, Tests, Analyses, and Acceptance Criteria

(ITAAC) for Operational Programs (Programmatic ITAAC).

4. Letter to John P. Kelly, The Ocean County Board of Chosen Freeholders, dated June 26,

2002, responds to request for assistance in ensuring residents of Ocean County that

Oyster Creek Nuclear Generating Station is at the proper state of heightened readiness

to respond to a security event at that site. 

5. Letter to Spencer Abraham, Secretary of Energy, dated June 26, 2002, responds to

request for a point of contact to help DOE prepare a report to Congress on the potential

external regulation of the DOE non-defense science laboratories. 

Federal Register Notices Issued

1. Advisory Committee on Reactor Safeguards Subcommittee Meeting on ThermalHydraulic Phenomena
July 24, 2002 ENCLOSURE P

Region II

Items of Interest

Week Ending July 19, 2002

Closed Predecisional Enforcement Conference

On July 15, 2002, Region II held a closed Predecisional Enforcement Conference with an

individual, who provides services for medical facilities. The purpose of this Conference was to

discuss apparent willful violations.

Dominion/Virginia Electric Power Company - North Anna Unit 1 Full Scale Emergency Exercise

On July 16, 2002, the Agency participated in an emergency preparedness exercise with the

licensee and representatives of the Commonwealth of Virginia and of other Federal Agencies. 

The exercise included the transfer of the NRC’s response from the Regional incident response

center to the NRC Headquarters Operations Center, and subsequently to the NRC Site Team. 

The Regional State Liaison Officer participated as a member of the FEMA team to evaluate the

performance of offsite Agencies during the exercise.

Gallup Survey Briefing for the Senior Managers

On July 17, 2002, a representative from the Gallup Organization briefed regional senior

managers on the results of the survey they conducted with managers and staff in Region II. 

The purpose of the survey was to obtain feed back on how engaged the managers and staff

perceived they are in Agency actions and decisions. Approximately 81percent of the Region II

employees participated in the survey. Gallup's typical participation rate is 77 percent. 

Additional briefings and training sessions will be held in August with Region II branch chiefs. 

This is part of the Office of Nuclear Material Safety and Safeguards and Regional initiative to

increase internal communications and employee engagement.
July 24, 2002 ENCLOSURE P

Region III

Items of Interest

Week Ending July 19, 2002

Manual Chapter 0350 Oversight Panel Meets on Davis-Besse

The Manual Chapter 0350 Oversight Panel for the Davis-Besse reactor vessel head damage

issue met July 16, 2002, with representatives of First Energy Nuclear Operating Company in

Oak Harbor, Ohio, to discuss the status of the utility’s vessel head replacement and other work

planned as part of the return to service program. The Panel also conducted an evening public

meeting to discuss the status of the NRC’s response to the head damage and to hear questions

and comments from members of the public. Transcripts of both meetings will be available on

the NRC web site.
July 24, 2002 ENCLOSURE R

Office of Congressional Affairs

Items of Interest

Week Ending July 19, 2002

CONGRESSIONAL HEARING SCHEDULE, NO. 62

OCA

Contact

DATE

&

PLACE

TIME WITNESS SUBJECT

Portner 07/22/02

Capitol

12:00 Markup FY03 Energy and Water

Development Appropriations

Senato

Energy

Approp

Keeling 07/24/02

SD-342

 9:30 Markup S. 2452, Dept. of Homeland Security Senato

Govern

Portner 07/24/02

Capitol

10:00 Markup FY03 Energy and Water

Development Appropriations

Senato

Approp

Keeling 07/25/02

Tentative

TBA Markup Jeffords/Reid Nuclear Security Bill Senato

Environ