Text

Summary of 990302-03 Meeting with NEI & Representatives of Dry Storage Industry Re Technical Issues Common to Storage & Transport of Sf,Including Lessons Learned,To Expedite Cask Certification Process
	ML20207A170
Person / Time
Issue date:	03/19/1999
From:	Reid D; NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Shankman S; NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
	NUDOCS 9905260175
	Download: ML20207A170 (120)
	v • d • e

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f j NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. -8 "1

,o March 19, 1999 MEMORANDUM TO: Susan F. Shankman, Deputy Director inspection and Licensing Directorate Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards ( ,

A FROM: Dennis G. Reid, Project Manager /f, 2.

,Ug Spent Fuel Licensing Section f Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards

SUBJECT:

SUMMARY

OF MARCH 2-3,1999, MEETING WITH NUCLEAR ENERGY INSTITUTE AND INDUSTRY On March 2-3,1999, the Nuclear Energy Institute (NEI) sponsored a meeting between I representatives of the dry storage industry and staff from the Nuclear Regulatory Commission's (NRC) Spent Fuel Project Office (SFPO). The meeting provided an open forum for discussions of technical issues that are common to the storage and transport of spent fuel, including l lessons leamed, to expedite the cask certification process. The public meeting was noticed on February 3,1999, and was held at the University Club in Washington, DC. Approximately 150 .

individuals were in attendance representing utilities, vendors, contractors, and fabricators.

To encourage open and candid discussions, the meeting was conducted in a workshop format.

Opening remarks were made by Lynnette Hendricks, Director, Plant Support, Nuclear Generation Division, NEl, and E. William Brach, Director, Spent Fuel Project Office, NRC. The major topics discussed were application and use of standard review plans (SRPs), dry cask storage lessons leamed, use and application of interim staff guidance (ISG), technical specifications, Part 72 rulemaking, ASME Code issues, and inspection observations, lf During the meeting, SFPO management discussed industry's and staff's progress and expectations in the licensing process. Issues discussed included:

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Staff will continue to apply lessons leamed from completed casework to facilitate both technical and process improvements

Quality of applications has improved significantly. However, several areas require continued improvement including ASME Code use, identification of SRP deviations, and specification of appropriate features on Part 71 drawings

Implementation of improved standardized technical specifications

The staff requested that any changes in application schedules be communicated prornptly, so that, resources can be efficiently utilized ,

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S. Shankman l

Applicants should bring unique designs and design features to the staff's attention early in the application process so that appropriate resources can be made available for a i timely review l l

In addition, SFPO management stated that SRP's serve as guidance to our reviewers and are l not the only way to meet regulatory requirements, and that the ISGs are used as interim guidance until SRPs are updated. The industry stated that issuance of ISGs has been a significant benefit to the vendors, and the industry is anxious to work with the staff to further clarity additionalissues.

The meeting included a round table discussion period wherein NRC staff responded to questions relating to certain specific topics deemed important by the industry. The topics included: ASME Code initiatives, design margin, uniformity of review, fission gas release fraction, and burnup credit. The industry presented an initiative it is pursuing to provide a standard licensing approach regarding ASME Code requirements. The Subgroup on Containment Systems for Spent Fuel and High Level Waste Transport Packagings anticipates publishing the new rules for WC within 18 months and making them effective 6 months after publication.

i The Workshop was continued on March 3,1999, with SFPO staff and industry discussing development of a plan to resolve open issues. The industry and NRC have agreed to schedule future meetings to continue the dialogue on a number of issues. The following is a list of ISGs that are currently under development and that will be provided to industry for comment in the near future: (1) fuel assemblies with burnup greater than 45,000 GWD/MTU, (2) rod buckling, (3) burnup credit, and (4) ASME Code deviations.

Industry Initiatives To expedite the cask certification process, the industry is pursuing the following initiatives:

1. Development of conservative source terms for fission products release

2. Develop rational for the demarcation between credible and non-credible accident scenarios.

3. Approaches for application of probabilistic risk approach (PRA) in licensing submittals -

the staff stated at the workshop that it encourages the use of PRA to provide for a risk-informed approach in the licensing process.

V-S. Shankman Uncomino Meetinas Because a number of issues were raised the require additional time for resolution, future meetings will be scheduled to discuss these topics:

)

Standardized Technical Specification -meeting scheduled for April 20,1999 in the NRC Auditorium

. ASME Code activities

. Classification of damaged fuel - NEl to provide additional information I

Lift heights (Part 50 vs. Part 72 requirements) - industry to provide more information Other issues were discussed at the meeting that were considered important. However, they were regarded as issues that could be addressed some time in the future. One issue relates to the integration of 10 CFR Parts 71 and 72 requirements. Specifically, the discrepancy between the certificate periods for transportation packages (5 years) and storage casks (20 years) and potential impacts the time differences may have in the review of dual purpose casks. The staff requested industry views on the draft ISG topics that were discussed and NEl accepted the responsibility to compile industry comments on the proposed ISGs and submit them to the staff by March 12,1999 (comments were received from NEl on March 12,1999). No regulatory decisions were requested or made. No proprietary information was disseminated.

Attachments: 1. Attendance List

2. NEl Slides '

3. NRC Slides i

DISTRIBUTION:

NRC File Center Public SFPO r/f NMSS R/F PMNS (e-mail)

EWBrach WHodges EEaston PEng RChappell LKokajko ENJensen, OGC SFTR/SFLS Staff (e-mail)

SGagner, OPA CFLyon, NRR G:\NEM99MTSUM *see previous concurrence orc: SFPO* E SFPO* E SFPO* E I NAME: DReid:Je VTharpe EJLeeds DATE: 3/19/99 3/19/99 3/19/99 OFFICIAL RECORD COPY

(

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Technical Review Directorate M. Wayne Hodges, Deputy Director Technical Section A Technical Section B Easton, Earl, Section Chief Leeds, Eric, Section Chief Barto, Andrew Bajwa, Chris Battige, Ken Brown, Chris Carlson, Donald Homseth, Geoffery i Colpo, Sarah Howe, Allen Gruss, Kim Huang, Daniel Guttman, Jack Interrante, Charles 4 Hogsett, Steven Kovacic, Joe Keegan, Elaine Lou, K.C.

Lee, Henry Meyers, Julia Parkhill, Ron Regan, Chris .

Tang, David Whaley, Sheena Yang,Li White, Bemie Vacant Wdhee, Carl Vacant i

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NEI Dry Storage Workshop March 2-3,1999 Washington, DC

( NEI Dry Storage Workshop March 2-3,1999 q

The University Club Washington, DC Agenda Tuesday, March 2,1999 8:30 a.m. - 5:00 p.m.

l

. Welcomelintroductions

. NEI Industry Opening Remarks Lynnette Hendricks, Director, Plant Support, Nuclear Generation Division

. NRC Opening Remarks William Brach, Director, Spent Fuel Project Office

. Workshop Conduct and Format Dennis Reid, Project Manager, NRC Alan Nelson, Senior Project Manager, Plant Support

. Topics for Discussion

1. Application and Use of the Standard Review Plan

. NRC Lessons Learned Susan Shankman, Deputy Director, Licensing & Inspection Directorate, NRC

. NRC's OverallImpression Since Issuance

. Industry Experience, Willington Lee, Vice President and Chief Engineer NAC International

2. Dry Cask Storage Applications Lessons Learned

. Industry Experiences David Bland, Project Manager, Hatch ISFSI Brian Gutherman, Licensing Manager, Holtec International

. NRC Expectations of Application Submittals e<

Discussion on Direct Final Rule Eric Leeds, Section Chief, Spent Fuel Licensing Section, hTC l

3. New Interim Staff Guidance, Use and Application

. Industry Experiences, Rita Bowser Deputy Director, Spent Nuclear Fuel Programs Westinghouse Electric Corporation

. New Interim Staff Guidance, Use and Application Wayne Hodges, Deputy Director, Technical Review Directorate, NRC

. What's New? Any lessons learned Since the Implementation ofISG's e Fuel Buckling

. High Burnup Fuel (> 45,000 MWD /MTU)

. Lunch: Noon-1:00 p.m.

4. Roundtable Discussions

Industry QA Oversight Programs Alan Nelson, Sr. Project Manager, NEI e Industry Fabrication, Examination and Testing Guidance Initiative Albert Machiels Program Manager, EPRI e Current ASME Activities Robert Nickell, Consultant

. NRC, Wayne Hodges Design Margin

-Uniformity of Review

-Fission Gas Release Fraction

-Burnup Credit (NRC Research)

5. Standard Tech Specs Dry Cask Storage

. NRC Approach to Standard Tech Specs Joseph Shea, Project Manager, Spent Fuel Licensing Section, NRC

. Industry Standard Technical Specification Approach Bryan Ford, Entergy, BWR Owners Group Technical Specifications Issues Coordination Committee Chairman Donald Hoffman, Excel Services Corporation

6. Part 72 Rulemaking,72.48

. Industry Approach to Part 72 John Dosa, Entergy l

7. Inspection Process, lessons Learned

. Industry Quality Oversight l

Jerry Delezenski, Manager, Quality and Compliance, SMUD Richard Slaten, Quality Engineer, SMUD

. Industry Lessons I. earned @SQG)

Thomas Dey, PECO Energy James Gill, Wisconsin Electric Power Co.

Dennis Kierpa, GPU Nuclear, Inc.

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4.

Wednesday, March 3,1999 8:30 a.m.-Noon 8:30 a.m.-10:00 a.m. Industry Discussion 10:00 a.m.-10:15 a.m. Break 10:15 a.m.-Noon Open Discussion: Industry /hTC i

r NEI Dry Storage Workshop Table of Contents Application and Use of the Standard Review Plan Tab 1 Dry cask Storage Applications Lessons Learned Tab 2 New Interim Staff Guidance, Use and Application Tab 3 Roundtable Discussions Tab 4 Standard Tech Specs-Dry Cask Storage Tab 5 Part 72 Rulemaking,72.48 Tab 6 Inspection Process, Lessons Learned Tab 7 Participants List Tab 8 1

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NEI Drv Storage Workshop hisreh 2 3,1999 The Universitt Club Washington", DC Application and Use of Standard Review Plans Industry Experience BillLee i1ce President and ChiefEngineer NACInternational

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g_3 StandardReview Plans l

a Standard Review Plan for Dry Cask Storage Systems,NUREG 1536.

January 1997.

m Standard Review Plan for Transportation Packages for Spent Fuel, (Draft for Comment), NUREG-1617. March 1998.

a Standard Review Plan for Spent Fuel Dry Storage Facilities, (Draft for Comment),NUREG-1567. October 1996.

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i HistoricalPerspective I a Transponation Package Licensing

- 10 CFR Part 71

- Cask Approvals on-going for nearly 40 years

- Process well defined for initial submittal requests for and amendments

- Many precedents established

- Currently over 25 cask systems licensed to transport spent fuel

- Numerous amendments approved pen. s hac INTin%ADON AL

. r Historical Perspective (Continued) e Storage Package Licensing /Cenification

- 10 CFR Part 72

- Two paths to follow - Site Specific or Certified Cask Design (General License)

- About a dozen cask systems are approved for storage of spent fuel

- First cask system approved in 1985 c

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C Historical Perspective (Continued) e Storage Facility Licensing

- 10 CFR 72 Regulations

- ISFSI in operation: 12 sites (including wet and dry storage facilities)

- Another 10 ISFSI are in planning or development ,

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..<,se.ar iE Historical Perspective (Continued) e Dual Purpose Systems

- 5 Cask System in review and approval process

- Priority to storage cask system review

- Storage and transportation regulation integration 4

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I Lessons Learned a SRP's are to be considered "living" documents

- Supplemented by Interim Staff Guidance Documents a SRP's establish expectations for all submittals

- Submittals are to be high quality

- States standard format requirements

- Compliance to Regulatory requirements

- States current NRC staff positions

- Lists the acceptable industry codes and standards

- States the acceptance criteria h AC INTlkNAIlON Ak P8tr

Lessons Leanted(Continued) e 10 CFR 71 is more prescriptive in stating requirements than 10 CFR 72

- 10 CFR 71 approval allows package to be used at any site

- 10 CFR 72 approval allows cask to be used at any

compatible site" e The use of SRP's has led to more uniformity in NRC staff reviews and a trore timely review process.

> a Standardization is developing.

1 a Compatibility between storage and transport i

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- Approval period duration (20 years for storage versus 5 year for transport)

- Cask conditions

Transpon-nonnal and accident conditions

Storage-normat. off nonnal and accident condition

- Storage approval amendment process need to be better defined l

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Applications Lessons Learned ' -

David W. Bland Chairman, Holtec Users Group Brian Gutherman Licensing Manager, Holtec International NEI Dry Cask Storage Workshop March 2,1999 .

Holtec International "cM N

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, i Ovenriew Communication with NRC Regulatory Guidance i Schedule .

' TechnicalIssues Summary 6 s 1

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Improvements Made rules of engagement 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months availabiht),48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months commitment letters frequency increased user group review & support RAI milestone communications post RAl. pre-response, post RAI response Lessons Learned different expectations request for data means comprehensive stor). leads to conniet Improvements needed two way street, mistakes on both sides, still not open enough 5

i Regulatory NUREG - 1536 guidance only - still developing (ISGs) both sides " interpreting" road map to compliance Be complete identify assumptions no gaps or leaps of faith Storage and transport same SAR review a audit review, not veri'fication self policing, design margins, robust designs 4

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l Schedule Time is exceptionally compressed large pressures i I

NRC SFPO is focused meeting schedule j Applicant performance focused resources required promise and deliver ,

compromise .

Full scale prototype :

subtle fabrication issues revealed & resolved fixturing & tooling process control test drive TechnicalIssues Technical Specifications 10CFR Part 50 ITS format, room for improvements, no selection criteria Storage pad requirements reference pad characteristics site-specille specification Lift heights for cask Part 50 versus Part 72, lift device qualifications Fuel specification level ofinformation detail i

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I expectations high schedules being met Landscape still developing regulatory positions regulatory oversight Design margin key l User group review & support i Give details and pointers Communication key still needs improvements on both sides I

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-; -Interim Staff Guidance

-Feedback

-Implementation ofISG

-Questions on Current ISG 1

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- Guidance on Key Issues is Extremely Helpful to Both Utilities and Vendors

Inurim Staff Guidance Requiring No General Clarifications Include:

-ISG 1 Dam ged Fuel

-ISG 2 Fuel Retrievability

-ISG 6 Minimum Enrichment for Design Basis

-ISG 7 Cask Heat Transfer

-Questions on Current ISG

-ISG 3 Post Accident Recovery

-How is credibility defined?

- Could PRA techniques be used?

-is the pal to remove all non-credible accidents, including tipover?

-ISG 4 Cask Closure Weld Inspection

- Status of NRC response to industry paper 2

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-? :-Questions on Current ISG (cont.)

-ISG 5 Accident Dose Calculations

- Assumed minimum leakage for a duration of one year based on extremely conservative source terms results in a significant over-estimation of dose to the public

- Leak tight testing is easier to specify than to perform

- Consider remedies (more realistic source term)

-: : -Summary

...=_ . - - . . . . , .

-ISG had been especially successful where j NRC and industry clearly communicated !

problems and possible resolutions (Damaged fuel) l

- Early discussion or notification makes j requirements more uniform and easier to

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- A " working list" ofISG in process would help I

3

Industrv Proposal

'C. Fuel Classification Protocols in the roundtable workshop held July 1-2,1998, general agreement was reached between the NRC and industry on the appropriate strategy to use in classifying and shipping fuel that had undergone either cladding er fuel assembly mechanical damage. The classification process would use the following criteria to determine what was " Damaged Fuel." Fuel would be classified as damaged ifit met at least one of the conditions called out in either of the two following categories.

Cladding Integrity - Fuel containing a breech of cladding greater than pinholes or hairline cracks such that there is the potential for the loss of signi6 cant fuel particulate

Mechanical Damage - Fuel assembly's structural integrity compromised such that special handling is required or assembly geometry no longer permits normal insertion or removal from standard size storage racks or canister baskets.

Once fuel has been classi6ed ks " Damaged Fuel," the fuel must be canned in a separate container that is designed to prevent the loss of fuel particulate but need not be a sealed, pressure-containing vessel.

In order to implement the agreed upon strategy, a system of procedures and protocols must be created to provide reasonable assurance that fuel is properly classified and any necessary corrective actions taken. At the workshop, the NRC requested the industry to formulate the procedures to provide proper fuel classi6 cation. The objective of these procedures is to provide ,

adequate assurance to the regulators and to the licensees that the fuel has been properly classified while at the same time not placing unnecessary and onerous burdens on the utilities. Below is an outline of the suggested classi6 cation procedures and protocols.

1. Records shall be created and maintained, following appropriate QA requirements, that record the various steps taken and the resulting outcome of the fuel classification process.

This record may be called the " Fuel Assessment Record." Separate deternunations to assess the status of cladding integrity and assembly mechanical damage shall be performed.

2. CladdingIntegrity A. Reactor Records

i. Use the reactor operating records to identify specific leakmg assemblies or to determine if there are likely to be any failures in a given fuel

. discharge. It is acknowledged that the type and quality of core performance and radiochemistry records vary from plant to plant and also with the age of the plant.

Each plant will specify which records will be used as the basis for mrking the failure classification decision.

ii Record the resuh ofthe operating records review by concluding one ofthe following for each assembly: a) non leaker, b) questionable leaker or no records

, available, or c) known leaker. Based on the determination, the following actions would be followed.

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a) Non lenker -permissable to ship and/or store without takmg any funher action.

b) Questionable leaker or no records available - additional verification required either in the form of special visual inspections or conducting a specific leak detection procedure, such as sipping or ultrasonic testing, that is judged to be the best practical technology to assess the fuel I

cladding integrity. It is recognized that the age of the fuel and the nature of some cladding failures makes leak testing a somewhat uncertain science. The results of any additional inspections or testing should be used to classify the fuel I as either a non-leaker or a lenker.

c) Leaker - provide additional data or analyses that suppons a conclusion that the cladding defect is minor in nature, typically charactenzed as a pin hole or hairhne crack that would not resuh in the loss of significant fuel I paniculate, and that the assembly can therefore be stored or shipped without taking any funher action. If this detennination cannot be reached, the assembly would be classified as " Damaged Fuel."

The detemunation made as the result of the Step 2.A process d) must be documented and signed off by at least two people, one who must serve in a quality verification capacity.

A. VisualInspection

i. A visual inspection will be performed in conjunction with the determination made in Step 2.A above. For a non leaking fuel assembly (a), this inspection need not include any special procedures or equipment other than the nonnal observations made dunng normal fuel handling and transfers. Such inspection would verify that the assembly was in normal geometry and had sustained no damage that might interfere with safe fuel handling and fuel movement. There would be no requirement for any film or video record and the only required documentation would be by exception for those assemblies observed to have sustained visible damage.

i ii. For categories b and c, this inspection would require the use of at least video equipment and the resuhs must be recorded on some medium such as video tape. Should an assembly be classified as " damaged" and a comnutment made to can the assembly, there would be no further visual inspections required.

iii. The results and conclusions of special visual inspections must be signed off by at least two people, one who must serve in a quality verification capacity.

A. Should a fuel assembly be classified as " Damaged Fuel" as a resuh of either 2.A or 2.B, the assembly shall be specirlly designated and placed under siTict administrative controls to insure that it will not be loaded pending either subsequent

.anning or funhet inspection activities. .

1. MechanicalDamage 2

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q A. The 'Tuel Assessment Record" shall include a detenanation, requiring signoff <

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C' from two people, one who must serve in a quality verification capacity, that the fuel

. meets the following two conditions:

i. Past history or current experience indicates that the fuel can be {

grappled and handled in a normal manner with no geometry interference detected 1 as the fuel was moved between storage spaces or into storage or transport baskets.

ii. Based on observations made in the visual inspections described in Part 2.B above, that there is no observable damage to the fuel bundle hardware, such as grid straps, end nozzles, etc. which indicate that the fuel requires any kind of special handling to insure safe and routine loading and unloading.

The completed 'Tuel Assessment Record" would become part of the fuel assembly's permanent record at the reactor site and would be available for routine NRC audit or inspection. It need not i be sent with the fuel upon shipment or need not become an addendum to other currently required regulatory paperwork such as the nuclear material accountability records.

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Independent Spent Fuel Storage Installation Quality Assurance {

NEI Dry Storage Workshop Washington, DC March 2,1999 Alan Nelson NEI NEI Dry Storage Quality Assurance

= Utility Responsibility

= Utility Dry Storage QA Activities

= Vendor Dry Storage QA Activities

= ISFSI QA Plan

= Design Control and Verification

= Procurement Control and Verification

= Fabrication Control and Verification NEl I

(

Standard Guidance Industry Initiativ NEI Dry Storage Workshop l March 2-3,1999 Alben J. Machiels Roben E. Nickell Topics Development of Guidance Document (Machiels)

Status of Activities Related to ASME Code,Section III, Division 3 (Nickell) 1

Guidance Document -- Background

Meeting held on February 24,1999

- Participation: Utilities (4); Designers (4);

Fabricators (4)

- Support for an industry initiative developing standard guidance

- Drafted objective; goals; scoping statement; preliminary list ofitems to be covered; process flow; participation; expectations; schedule l

Guidance Document -- Objective To provide standard guidance to an independent third-party, which enables the reviewer (s) to ensure that the licensing / design basis requirements are met throughout the design, fabrication, examination, and testing process

. . . . . . . e l 2

C Guidance Document -- Goals Ensure safety and quality Provide consistency Optimize use ofNRC and utility resources l

Guidance Document -- Scope !

The scope of the guidance document covers items important to safety in dry spent fuel storage and transportation systems, with an emphasis on the incorporation of design into fabrication, examination, and testing requirements c

)

Guidance Document -- Scope (cont.'d)

Canister / Cask Concrete Overpack Transfer / Transport Systems Guidance Document -- Participation Utilities; Designers; Fabricators Observers: NRC; ASME; ANSI; Third-Panies; ...

4

Guidance Document -- Process Flow Review of SAR's; SRP's; Fabrication sequences and records Emphasis on functional testing Phased approach Guidance Document -- Expectations Preparations of EPRI report (s) submitted to NRC through NEI for endorsement by NRC If appropriate, incorporation of the endorsed EPRI documents in industry standards e

j l

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Guidance Document -- Schedule Preparation of draft guidance report (Phase 1) and readiness to provide a detailed briefing in September 1999 l

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NEl DRY STORAGE WORKSHOP The University Club l Washington, DC March 2-3,1999 INDUSTRY GUIDANCE INITIATIVE-STANDARD APPROACH, EPRI ALBERT MACHIELS, PROGRAM MANAGER, EPRI ROBERT E. NICKELL, CONSULTANT, EPRI EPRI I

ASME CODE SECTION lit. DIVISION 3

. The Subgroup on Containment Systems for Spent Fuel and High Level Waste Transport Packagings (SG NUPACK, SC lil) has modified its scope to include storage canister construction rules

The rules will covar " confinement boundary" items only, and will be placed in a new Subsedion WC of Division 3 (Subsection WA contains General Requirements and Subsection WB contains rules for transport cask containment boundary items stamped TP)

.

The confinement boundary will be stamped SP

+ SG NUPACK is also considering a new Subsection WD covering rules for processing (?) and storage of high level waste EPRI i

ASME CODE SECTION lli. DIVISION 3

SG NUPACK voted on February 23,1999,in Birmingham, AL, to

" Fast Track" the Subsection WC rules

SG NUPACK also will be maintaining a much closer relationship with the SC lil Subgroup on General Requirements (NCA), so that only the essential deviations between NCA and WA will exist

The Subsection WC rules will be patterned after Subsection NC rules of Division 1, except that " design by analysis" rules will be followed (NC 3200)

In addition, the special requirements for weld joints in vessels designed to NC 3200 (NC 4260) will be adopted EPRI ASME CODE SECTION lli. DIVISION 3

John Stevenson, Chair, SG NUPACK, will select a fast track project manager

Schedule is such that the first draft of the rules will be available by the May 1999 meeting of SG NUPACK in Greensboro, NC

Rules will be written wherever possible by reference to existing rules in the ASME Code e Rules will follow existing Subsection WA scope requirements for the third party inspection agency, for the Class TP (SP) i Certificate Holder, and for the Dasign Owner and the Packaging !

own.r j l

EPRI l I

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. . . - - . - - ._____ _ ______ __ ___J

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C ASME CODE SECTION lil. DIVISION 3

The Design Owner is the organization which obtains a Certificate of Accreditation issued by ASME, prepares (or causes to be prepared) a Design Specification, determines the loads, designs the confinement boundary, demonstrates the adequacy of the confinement boundary design, and issues a Design Report

. The Packaging Owner is the organization which assumes title to the storage packaging upon delivery by the Class SP Certificate Holder

. The Packaging Owner (or designee) initiates construction of the confinement boundary through the issuance of a Construction Specification EPRI ASME CODE SECTION 111. DIVISION 3

The Class SP Certificate Holder is the organization which constructs the confinement boundary as part of the storage packaging in accordance with the requirements of the Construction Specification

The Class SP Certificate Holder obtains an N type Certificate of Authorization from the ASME, completes the appropriate Data Report Form, and applies a Code Symbol Stamp to the completed confinement boundary of a storage packaging C

EPRI 3

ASME CODE SECTION 111. DIVISION 3

The duties of the Authorized Nuclear inspector are covered in WA-5200

The Inspector shall witness or otherwise verify all examinations and make all inspections required by this Division. The Inspector shall also make any other inspections and witness or verify any other examinations and additional investigations which are necessary to ascertain whether the item being inspected has been constructed in compliance with the rules of this Division

The inspector shall verify that the Design Specification, Design Reports, etc. are on file and are properly certified, but is not responsible for the completeness or adequacy of these documents EPRI O

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3.1 SSSC INTEGRITY 3.1.3 SSSC Hefium Leak, Rate LCO 3.1.3' The SSSC helium leak rate for all closure seals shall not exceed the limit specified in Table 3-1 for the applicable SSSC design.

APPLICABILITY: During LOADING OPERATIONS.

ACTIONS

- NOTE Separate Condition entry is allowed for each SSSC.

CONDITION REQUIRED ACTION COMPLETION TIME A. SSSC helium leak rate limit A.1 Establish SSSC helium leak rate 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months not met. within limit.

I B. Required Action and B.1 Remove all fuel assemblies from 7 days Associated Completion the SSSC.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify SSSC helium leak rate is within limit. Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after verifying SSSC helium backfill pressure is within limit.

s North Anna ISFSl3.1.31 l

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SE A RTC I

WV CNHA _

G Technical Specifications for Dry Fuel Storage i

Bryan Ford i Entergy NEl Workshop March 1999 Purpose of Technical Specifications The Commission's Policy

+

The purpose of Technical Specifications is to impose those conditions or limitations upon reactor operation necessary to obviate the possibliity of an abnormal situation or event giving rise to an immediate threat to the oublic health and safety by establishing those conditions of operation which cannot be changed without prior Commission approval and by identifying those features which are of controIIIno Importance to safety.

i O

Part 50 Experience before ITS

+ A new plant's Tech Specs where developed case-by case based on what was approved for the last plant

+ Personalitiss influenced the product causing inconsistencies between licensees

+

+ Schedule pressures many times influenced decisions

+

+ Without defined criteria the trend was towards including essentially all Commission requirements and the resolution to all issues

+

Part 50 Result The Commission's Conclusions y The Technical Specifications become so controlling of all aspects of plant operation that unneeded requirements in the Technical Specifications were diverting both staff and licensee attention from the more important requirements to the extent that the excessive requirements "resultedin an adverse but unavantifiable imosct on safetv".

More is not always better l

(

E Part 50 Improvement Process

+ Developed human factor format, style, and usage rules.

+ Generic continuous improvement process

_ NEl/NRC TSTF process

Developed the 50.36 Tech Spec selectior. criteria

+ Focusing the Tech Specs on the Operator results in in Tech Specs focused of immediate threats to the public

+ ,

Status of ISFSI Technical Specifications

+ Some of the human factor format, style, and usage rules need consistent application

+ Part 72 and a sarnple of Tech Specs show the lessons learned

! in Part 50 need to be applied

What Should Stay Conditions or limitations necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety

+ LCOs and SRs of controlling importance to safety

- Integrity LCOs

+ Design features which realistically may be changed by the operating staff and pose an immediate threat e

What Should Go Conditions or limitations not associated with an immediate threat to the public health and safety e

+ ltems controlled by regulations

- Part 20 ALARA

- Reporting requirements e items controlled by the QA Plan

- Procedures '

- Training

! - Design e!,ments controlled by the purchasingfengineering procesu

(. ~

Other improvements . . . _

+

+ Remove the Bases from the C of C and allow 72.48 changes

... +

+ Develop a Tech Spec template for vendorslutilities to use

+ Rigorously apply Tech Spec format and usage rules

- Remember SRs must be met (unless excepted) whenever you are within the LCO Applicability regardless of the frequency l

Conclusions

+ Tech Specs must focus on safety

+ More is not always better

.

Rules are needed to keep Tech Specs focused on safety

+ Risk to the public and workers is lower for dry fuel storage than operating reactors.

Tech Spec requirements not needed for power reactors are not needed for dry fuel storage

+ Part 72 Tech Specs should learn from Part 50 Tech Specs lessons learned

+

l

1 APPLICATION OF INDUSTRY POWER PLANT IMPROVED TECHNICAL SPECIFICATIONS i EXPERIENCE TO ISFSI/ CASK TECHNICAL SPECIFICATIONS ;

DONALD R. HOFFMAN PRESIDENT EXCEL SERVICES CORPORATION NEI DRY STORAGE WORKSHOP MARCH 2-3,1999 WASHINGTON D.C. i CUSTOM AND STANDARD TECHNICAL SPECIFICATION EXPERIENCE

. IN CUSTOM TECHNICAL SPECIFICATIONS, A NEW PLANT'S TECHNICAL SPECIFICATIONS WERE DEVELOPED BASED ON WHAT WAS APPROVED FOR THE LAST PLANT LICENSED

. IN STANDARD TECHNICAL SPECIFICATIONS, THE LAST PLANT LICENSED TECHNICAL SPECIFICATIONS SOON BECAME THE STANDARD

. DIFFERENT NRC/ PLANT PRIORITIES AND CAPABILITIES INFLUENCED THE TECHNICAL SPECIFICATIONS CONTENT CREATING SIGNIFICANT INCONSISTENCIES

(

. LICENSING SCHEDULE PRESSURES OFTEN INFLUENCED DECISIONS 1

CUSTOM AND STANDARD TECHNICAL SPECIFICATION EXPERIENCE

NO REAL BASIS FOR MANY ALLOWED OUTAGE TIMES (AOTs) AND TEST INTERVALS (STrs) EXISTED

+ THE RESULT OF NO DEFINED CRITERIA WAS THE TECHNICAL SPECIFICATIONS INCLUDING ESSENTIALLY ALL NRC REQUIREMENTS

+ MANY TECHNICAL REQUIREMENTS LACKED BASIS THE REQUIREMENTS WERE INTERNALLY INCONSISTENT

+ THE USAGE RULES WERE UNCLEAR AND OFTEN MISAPPLIED RESULTS AND COURSE OF ACTION THE THEN CURRE :T CUSTOM AND STANDARD TECHNICAL SPECIFICATIONS RESULTED IN SUCH A DIVERSION OF NRC AND LICENSEE ATTENTION AND RESOURCES THAT THERE WAS ADVERSE BUT UNQUANTIFIABLE IMPACT ON SAFE"IY

+ THE NRC AND INDUSTRY UNDERTOOK AN IMl ROVED TECHNICAL SPECIFICATION (ITS) PROGRAM

+ INTENT OF ITS PROGRAM WAS TO DETERMINE WHAT WAS s

APPROPRIATE FOR INCLUSION IN THE TECHNICAL SPECIFICATIONS AND TO FIX/ CLARIFY / UPGRADE THOSE REQUIREMENTS BEING RETAINED IN TECHNICAL SPECIFICATIONS 2

C MAJOR OBJECTIVES OF IMPROVED TECHNICAL SPECIFICATIONS IMPROVE SAFETY I PROVIDE CLEARER UNDERSTANDING OF SAFETY SIGNIFICANCE EASE NRC AND INDUSTRY ADMINISTRATIVE BURDENS l

ITS CHRONOLOGY l '

1954 SECTION 182.a ATOMIC ENERGY ACT(ACT) 1968 10 CFR 5036 1974 STANDARD TECH SPECS 1983 TASK GROUP 1987 NRC INTERIM POLICY STATEMENT 1988 NRC " SPLIT REPORT" 1989 OWNERS GROUPS DRAFTS 1991 NRC DRAFTITS 1992 NRC ITS NUREGS REVISION O ISSUED 1993 NRC FINAL POLICY STATEMENT 1995 NRC ITS NUREGS REVISION I ISSUED l

1995 NRCITS RULE e 1995-PRESENT PLANTS CONTINUED TO CONVERT TO ITS AND TECHNICAL SPECIFICATION TASK FORCE (TSTF) '

CONTINUED TO MAKE GENERIC IMPROVEMENT TO THE ITS NUREGS l l

3

)

SPLIT CRITERIA CRITERlON 1: INSTALLED INSTRUMENTATIG J THAT IS USED TO DETECT, AND INDICATE IN THE CONTROL ROOM, A SIGNIFICANT ABNORMAL DEGRADATION OF THE REACTOR COOLANT PRESSURE BOUNDARY CRITERION 2: A PROCESS VARIABLE, DESIGN FEAFURE, OR OPERATING RESTRICTION THAT IS AN INITIAL CONDITION OF A DBA OR TRANSIENT ANALYSIS THAT EITHER ASSUMES THE FAILURE OF OR PRESENTS A CHALLENGE TO THE INTEGRITY OF A FISSION PRODUCT BARRIER 4

SPLIT CRITERIA CRITERlON 3: A STRUCTURE. SYSTEM, OR COMPONENT THAT IS PART OF THE PRIMARY SUCCESS PATH AND WHICH FUNCTIONS OR ACTUATES TO MITIGATE A DBA OR TRANSIENT THAT EITHER ASSUMES THE FAILURE OF OR PRESENTS A CHALLENGE TO THE INTEGRITY OF A FISSION PRODUCT BARRIER CRITERION 4: A STRUCTURE, SYSTEM, OR COMPONENT WHICH OPERATING EXPERIENCE OR PROBABILISTIC RISK ASSESSMENT HAS SHOWN TO BE SIGNIFICANT TO PUBLIC HEALTH AND SAFETY l

l l 4

1 l

ADDITIONAL SPLIT APPLICATION 1

I IN ADDITION TO THOSE STRUCTURES, SYSTEMS, AND COMPONENTS CAPTURED BY THE ABOVE CRITERIA, IT IS THE COMMISSION'S POLICY THAT LICENSEES RETAIN THEIR TECHNICAL SPECIFICATIONS' LCOS. ACTION STATEMENTS, AND SURVEILLANCE REQUIREMENTS FOR THE FOLLOWING SYSTEMS (AS APPLICABLE) WHICH OPERATING EXPEPJENCE AND PROBABILISTIC RISK ASSESSMENT HAVE GENERALLY SHOWN TO BE l IMPORTANT TO PUBLIC HEALTH AND SAFETY: (

l RCIC, RH1 SLC. RPT, AND ANY RISs( SIGNIFICANT SYSTEM (PRA) l OBSERVATIONS ON CURRENT ISFSI/ CASK TECHNICAL SPECIFICATIONS DUPLICATION OF REGULATIONS

+ INCLUSION OF ITEMS THAT ARE NOT APPROPRIATE OPERATIONAL LIMITATIONS EACH VENDOR HAS VENDOR SPECIFIC REQUIREMENTS RESULTING IN VERY LITTLE STANDARDIZATION IN THE 1 TECHNICAL SPECIFICATIONS

. MANY TECHNICAL AND ADMINISTRATIVE REQUIREMENTS SHOULD BE UNDER LICENSEE CONTROL AND NOT IN THE TECHNICAL SPECIFICATIONS 5

OBSERVATIONS ON CURRENTISFSI/ CASK TECHNICAL SPECIFICATIONS

+ MANY OF THE TECHNICAL AND ADMINISTRATIVE REQUIREMENTS THAT SHOULD REMAIN IN THE TECHNICAL SPECIFICATIONS ARE NOT STRUCTURED PROPERLY

+

INTERNAL INCONSISTENCY OF PRESENTATION AND REQUIREMENTS SUGGESTED ACTIONS TO IMPROVE ISFSI/ CASK TECHNICAL SPECIFICATIONS

+ BUILD ON THE POWER PLANT GENERIC ITS EXPERIENCE

TAKE MAXIMUM ADVANTAGE OF EXISTING PLANT SPECIFIC POWER PLANT ITS PROGRAMS

- DEVELOP AND MAINTAIN A STANDARDIZED SET OF TECHNICAL SPECIFICATIONS FORISFS1 AND CASKS

+

FOCUS ON THOSE REQUIREMENTS NECESSARY TO SAFETY

PROVIDE FOR OPERATIONAL / ADMINISTRATIVE FLEXIBILITY

. MODIFY RULES THAT WOULD REQUIRE TECHNICAL SPECIFICATIONS TO FOCUS ON REQUIREMENTS NOT RELATED TO SAFETY 6

(- .

Industry Comments: )

- Part 72 Changes Related to 50.59 Rulemaking I John Dosa l

(

Entergy i NEl Workshop March 1999 l I

4 I

Introduction

The proposed rulemaking to revise 10CFR50.59 also includes many proposed changes to 10CFR72.

+ The proposed changes did not make 10CFR72.48 consistent with 10CFR50.59.

+

+ Other changes were proposed beyond those necessary to revise 10CFR72.48.

+

+ Most industry comments adopted in SECY 99-054 e

/

10CFR72.48/10CFR50.59 Consistency

+ The current and initially proposed 10CFR72.48 were not consistent with 10CFR50.59

- Seven review criteria for 10CFR50.59 vs. nine for 10CFR72.48

. Significant increase in occupational exposure

. Significant unreviewed environmentalimpact l - Annual report of 10CFR72.48 evaluations for cask changes vs. biennial for changes to reactor systems

+ The process for making changes to casks or reactors should 1 be consistent. SECY.99 054 increases consistency.

Amendment Process

+ Changes are proposed to specify that 10CFR72.48 applies to site-specific and general licensees, as

=

well as certificate holders.

+ 10CFR72.48 revisions are proposed to allow site-specific licensees, general licensees, and certificate holders to make amendments if the criteria in 10CFR72.48 not met.

+

+ Proposed 10CFR72.244 has not been revised to

include generallicensees l

l i

l l

2 l

SAR Update Requirements

Site-specific cask SARs currently require annual updates vs.

biennial for reactors

- Burdensome updates every six months prior to use

+ Proposed requirements for annual SAR updates for general licensees and certificate holders

- No schedule for 1st update (10CFR72.248)

- No cutoff date for information to be included in SAR

, updates

+ Proposed requirements to describe the effects of changes

, made to the SARs causes significant additional burden

,

Proposed wording of SAR update regulations for casks provide different emphasis than 10CFR50.71(e) for reactors

+

10CFR72.48 Equivalent for Part 71

+ No equivalent process to 10CFR72.48 to make changes to transportation cask SARs has been proposed

+

+ Process of increased importance due to near term

, issuance of dual purpose cask licenses

- Changes made under 10CFR72.48 for storage .

may also affect transportation SAR (which l requires NRC approved amendment) l

+ New Staff proposal for supplemental rulemaking 3

)

l Conclusions i

+ Proposed changes to Part 72 should be consistent with Part 50 l

l

+

l

Changes should a, Iso provide consistency between site-specific and general licensees, as well as certificate holders

+

+ Most ofindustries comments on the proposed i

rulemaking have been adopted by the Staff I

l 4

( '

Rancho Seco QualityInitiatives Quality -- %

The Key to a Good " Tasting" Spent FuelStorage System NEl Dry Storage Workshop March 2,1999 3799 NEl Dry Storage Workshop 1 Rancho Seco Spent Fuel Storage System M

1 Based on the NUHOMS system

- MP-187 transportation cask"(1)

- Dry Shielded Canisters (21)

- Concrete Horizontal Storage Modules (22) j Training cask & canister l

No cask storage l

3t993/2/96 NEl Dry Storspe Workshop 2 1

Rancho Seco Spent Fuel Storage System

- Twenty-one DSCs M

- 18 FC-DSCs (fuel with control componen.s)

- 2 FO-DSCs (fuel w/o control components)

- 1 FF-DSC for damaged fuel

- Twenty-two concrete storage modules

- Twenty-one spent fuel canisters

- One optional for GTCC Waste NEl Dry Storage Workshop 3 3/3'993/2/99 Project Status

~

Y. -

- Transportation C of C

-Issued Sept. '98

- Storage SAR, Rev. 2 submitted Jan. '99

- Cask & canister fabrication Mar. '99

- Training cask / canister out for bid wEi ory stors9. wor =ino, 4 us93 2 e9 i

2 1

( '

Rancho Seco Goals Y~

- Decommission safely and economically Place spent fuel into dry storage

- stand-alone dry fuel storage facility

- Ability to transpon off site w/o repackaging

- Begin fuel offload December 1999

- Shut down spent fuel poolin 2001 1

- Terminate 10 CFR 50 license by 2012 3/3/993/2/99 NEl Dry Storage Workanop 6 Rancho Seco QualityInitiatives N'

The Question is: !

"Do you want a dry '

storage system that has .

good taste? Or, a ;

storage system that ;

tastes good?" .

l l

3T9931'99 net Dy storoet Wortsnos 6 1

3 I

l

f Rancho Seco QualityInitiatives a.

'N 7 To meet high Q standard, we required thorough review of vendor:

- Design drawings .

- Design specifications

- Q category assessment for each piece part l - Engineering calculations and changes 3/3'991 799 NEl Dry Storage Workshop 7 Rancho Seco QualityInitiatives N

High Quality Standard demands:

- Early involvement on all project activities

- Panicipation in designer / fabricator interface

- Competent / experienced staff for adequate oversight

- Intrusive presence at vendor and fabricators

- Questioning attitude l

3'3'983 ? 99 net Dry Storage Workshcp e 4

1 - _ _

C .

Rancho Seco QualityInitiatives 4

Place a resident QA surveillant at the fabricators Provide qualified third-party oversight of fabrication activities Participate in DSQG audit of our A/E Audited vendor as member of owners group 3/3/993/2/99 NEi Dry Storspe Workshop 9 Rancho Seco QualityInitiatives N

- Due to our intrusive Q oversight, Owner's Group involvement and NRC inspections, we believe MP-187 design:

- Will meet license conditions;

- Will be built to high Quality standards; and

- Will safely store spent fuel. l 37193/299 NEi Dfy Storspe Wortsnop 10-5 v

Project Results N

- NRC/ Utility QA concerns resolved

- TNW design re-verification and re-analysis completed

-NUHOMS Owners Group - Standard NUHOMS system

- SMUD - MP-187 transportable system 11 3/3/993/2/99 NEl Dry Storage workshop Summary A -

Fuel offload target - Dec. '99 With the Quality initiatives taken, Rancho Seco will have a spentfuel storage system that not only has good " taste", but " tastes" good!

net Dry Storage Womshop 12 3'31932/99 l

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. NEI DRY STORAGEWORKSHOP G March 2-3,1999 m The University Club a Washington, DC Participant List Glenn Adarns Joseph F. Andrescavage Senior Engineer Program Manager, Spent Fuel Wisconsin Electric Power Company GPU Nuclear, Inc.

231 W. Michigan Avenue Oyster Creek Nuclear Generating Station Milwaukee, WI 53201 P.O. Box 388 phone: (414) 221-4691 Forked River, NJ 08731 fax: (414) 221-2010 phone: (609) 971 4862 e mail: glenn. adams %wepco.com fax: (609) 971 4449 e mail: jandrescavage@gpu.com ,

Kenneth A. Ainger l Director. Decommissioning and Licensing Steven Baggett Commonwealth Edison Company Project Manager >

Suite 500 U.S. Nuclear Regulatory Commission 1400 Opus Place MS 06F18 Downers Grove. IL 60515 Washington, DC 20555 phone: (630)663-7350 phone: (301) 415-8584

, fax: (630)663 7155 fax: (301) 415 8555 ,

e-mail: aingeka&ccmail. ceco.com l Marissa Bailey William Alberque Project Manager Nuclear Programs Analyst U.S. Nuclear Regulatory Commission l Numark Associates MS 0-6F18 l Suite 715 Washington, DC 20555 1150 Connecticut Avenue, N.W. phone: (301) 415 8531 Washington. DC 20036 fax: (301) 415 8555 phone: (202:466 2700 e mail: mgb8nre. gov l fax: (202)466 3669 e mail: walberque&numarkassoc.com Treva N. Ballard Administrative Assistant C. K. Anderson Nuclear Energy Institute President Suite 400 CKA associates 1776 I Street, N.W.

241 Wright Road Washington, DC 20006 3708 Colhnsville. CT 06022 phone: (202) 739 8106 phone: (860i693 1313 fax: (202) 785-1898 fax: (860)693-1344 e-mail: tub 8nei.org e mail: chaassociates3 ibm. net Doreen Barta Licensing Engineer e Alliant Energy 3313 DAEC Road Palo,IA 52324 phone: (319) 851 7277 fax: (319) 851 7364 e mail: doreenbarta8alliant-energy.com NEI W

SPONSORED BY THE NUCLEAR ENERGY INSTITUTE

Robert H. Beall Kenneth W. Brown Senior Engineer Fuel Procurement Specialist Baltimore Gas and Electric Company Virginia Power

)

Calvert Cliffs Nuclear Power Station 5000 Dominion Boulevard 1650 Calvert Cliffs Parkway Glen Allen, VA 23060 6711 Lusby, MD 20657 phone: (804) 273-3563 phone: (410)495-4018 fax: (804) 273-3543 fax: (410)495 4498 e mail: Kenneth_ Brown @vapower.com e mail: robert.h.beall&bge.com Donald E. Carlson David Bland Senior Criticality Engineer Project Manager U.S. Nuclear Regulatory Commission Southern Nuclear Operating Company / ARC MS 0-6F18 P.O. Box 1295 Washington, DC 20555 Birmmgham, AL 35242-0355 phone: (301) 415-8507 phone: (205) 992-6697 fax: (301) 415-8555 fax: (205) 992-0362 e mail: decl@nrc. gov e-mail: david.w. bland @southerneo.com Ross Chappell David C. Blee Chief. Package Certification Section Executive Vice President U.S. Nuclear Regulatory Commission NAC International 11555 Rockville Pike Smte 200 Rockville, MD 20852 655 Engineering Drive phone: (301) 415-8510 Norcross. GA 30092 fax: (301)415 8555 phone: (770)447 1144 e-mail: crcl@nre. gov fax: (770) 447-6577 e mail: dblee@nacintl.com John Cook Senior Transportation Specialist Rita C. Bowser U.S. Nuclear Regulatory Commission Deputy Director, Spent MC O 6F18 Fuel Programs Washington, DC 20555 Westinghouse Electric Corporation phone: (301)415-8521 Suite 1200 fax: (301)415 8555 600 New Hampshire Avenue N.W.

Washington, DC 20037 Marshall David phone: (202) 945-6458 Program Manager fax: (202) 945 6404 Scientech, Inc.

e mail: bowserr@ westinghouse.com 910 Clopper Road Gaithersburg, MD 20878 E. William Brach phone: (301) 258 1868 Director, NMSS/SFPO fax: (301) 258-2570 U.S. Nuclear Regulatory Commission e mail: mdavid3scientech.com 11555 Rockville Pike MS 06F 18 Max M. DeLong Rockville, MD 20852 Executive Engineer phone: (301) 415 8500 Northern States Power Company fax: (301) 415-8555 414 Nicollet Mall (RS 7) e mail: ewbante. gov Minneapolis, MN 554011993

phone: (612) 330 5850 fax: (612) 330-5958 e mail: max.m.delongEnspeo.com 2

1 b

1 Jerry Delezenski Patricia L. Eng

(, Superintendent, Nuclear Licensing Sacramento Municipal Utility District Chief, Inspection Section, SFPO U.S. Nuclear Regulatory Commission 14440 Twin Cities Road M/S O 6 F 18 Herald, CA 95638 Washington, DC 20555-0001 phone: (916) 732 4914 phone: (301) 415 8577 fax: (209) 748 2244 fax: (301) 415 8555 e mail: jdeleze$smud.org e mail: ple3nre. gov Tom Dey Matthew L. Eyre PECO Energy Company Fuel Projects Engineer Box 2300 PECO Nuclear Mail Code SSB4 5 965 Chesterbrook Boulevard,62A 5

. Sanatoga, PA 19464 Wayne, PA 19087 5691 phone: (610) 718 3908 phone: (610) 640-6829 fax: (610) 718 3927 fax: (610) 640 6797 e-mail: tdey@peco-energy.com e mail: meyre%peco-energy.com John Dosa Bryan Ford Nuclear Safeiy and Licensing Engineer Senior Staff Engineer Entergy Operations, Inc. Entergy Operations, Inc.

1448 S.R. 333 1340 Echelon Parkway Russelh-ille, AR 72802 Jackson,MS 39213 8298 ,

phone: (501) 858-4621 phone: (601) 368 5792 fax: (501) 858 4685 fax: (601) 368-5768 e mail: jdosa8entergy.com e-mail: bford3entergy.com John Duffy David J. Foss Sales Lead Station Representative RANOR. INC. PECO Nuclear P.O. Box 458 PBAPS 1848 Lay Road Westminster. MA 01473 Red Lion, PA 17356 phone: (978) 875-0591 phone: (717) 456 4311 fax: (978) 874 2748 fax: (717)456 3433 e mail: jduffy@ranor.com e mail: dioss@peco-energy.com Earl P. Easton Vince Gilbert Section Leader Senior Project Manager, Operations U S. Nuclear Regulatory Commission Nuclear Energy Institute ;

Mail Stop 6E19 Suite 400 Washington, DC 20555 0001 1776 I Street, N.W.

phone: (301) 415 8520 Washington, DC 20006 3708 fax: (301)415 8555 phone: (202) 739 8138 e mail: exe@nrc. gov fax: (202)785 1898 e mail: jvg@nei.org Robert G. Eble, Jr. ,

Engineering Supervisor Jim Gill Duke Engineering & Services Senior Engineer, QA 2650 Park Tower Drive Wisconsin Electric Power Company ,

Vienna, VA 22180 231 West M2chigan Street phone: (703) 204 8657 Milwaukee, WI 53203 fax: (703)204 3880 phone: (414) 2212824 e mail: robert.ebleErw. doe. gov fax: (414) 221 3960 e mail: np2446@wepco.com 3

W..-

i 4

Alan J. Gould Brian Gutherman Senior Staff Specialist Director Of Licensing Florida Power & Light Company Holtec International P.O. Box 14000 555 Lincoln Drive West Juno Beach, FL 33408 Marlton, NJ 08053 phone: (561) 694-4199 phone: (609) 797-0900 X668 fax: (561) 694 3972 fax: (609)797 0909 e mail: al_gould8email.fpl.com e mail: brian _gutherman8holtec.com Harold Gray Stephen Guthrie Senior Reactor Engineer Project Manager U.S. Nuclear Regulatory Commission Consumers Energy 475 Allendale Road 10269 US 31 N.

King Of Prussia. PA 19406 Charlevoix, MI 49720 phone: (610) 337 5325 phone: (616)547 8254 fax: (616) 547 8246 Thomas A. Green Senior Technical Project Manager Ed Hackett GE Nuclear Energy Section Chief, Materials, 175 Cunner Avenue Office of Research U.S. Nuclear Regulatory Commission Mail Code 182 San Jose. CA 95125 MS T 10 E10 phone: (4081925-1308 Washington, DC 20555 fax: (408)925-2476 phone: (301)415 5074 e mail: thomas. green % gene.ge.com e-mail: emhi@nre. gov Robert M. Grenier James R. Hall President Senior Project Manager Transnuclear West Inc. U.S. Nuclear Regulatory Commission Suite 280 MS 06F18 39300 Civic Center Drive Washington, DC 20555 Fremont. CA 94538 phone: (301)415 1336 phone: (510) 744 6020 fax: (301)415 8555 fax: (510) 744 6086 e mail: jrh@nrc. gov e mail: robert.grenier8tn west.com Alan S. Hanson Kimberly Gruss President and Chief Executive Officer Materials Engineer Transnuclear, Inc.

U.S. Nuclear Regulatory Commission Four Skyline Drive M/S 06 F18 Hawthorne, hT 10532 Washington. DC 20555 phone: (914) 347 2345 phone: (301)415 8586 fax: (914) 347 2346 fax: (301)415 8555 e-mail: alan.hanson@transnuclear.com e mail: kaglanre. gov Christopher E. Hartz Brian Gustems QA Engineer Pnnespal Nuclear Engineer Pacific Gas and Electric Company Pubhc Service Electric and Gas Company P.O. Box 56 Avila Beach, CA 93401 P.O. Box 236

Hancocks Bndge. NJ 08038 phone: (805) S45 4032 phone: (609)339 1278 e mail: cehl&pge.com fax: (609) 339 1234 e mail: bgustemsspseg.com 4

I John D. Haseltine Wayne Hodges

( Director, Stategic Planning Connecticut Yankee Atomic Power Comp.any 362 Injun Hollow Road Deputy Director, Technical Review U.S. Nuclear Regulatory Commission 11555 Rockville Pike East Hampton. CT 06424 3099 Rockville. MD 20852 2738 phone: (860)267 3601 phone: (301)415 2398 fax: (860)267 3550 fax: (301) 415-8555 e mail: haseljd3gwsmtp.nu.com e-mail: mwhEnre. gov Lynnette Hendricks Donald R. Hoffman Director, Plant Support President j Nuclear Energy Institute EXCEL Services Corporation Suite 400 Suite 100 i 17761 Street, N.W. 11921 Rockville Pike Washington, DC 20006-3708 Rockville, MD 20852 2737 phone: (202) 739-8109 phone: (301)984 4400 fax: (202)785 1898 fax: (301) 984 7600 e mail: 1xhanei.org e-mail: donaldhgexcelservices.com Bill Hennessy Steve Hogsett Licensing Manager Nuclear Engineer Stone & Webster Engineering Corporation U.S. Nuclear Regulatory Commission 7077 E. Berry Avenue Mail Stop: 06F18 Enclewood, CO 801112137 Washington, DC 20555 0001 phone: (303)741-7430 phone: (301) 415 8537 fax: (303) T417806 fax: (301) 415-8555 t m ail: william.hennessy&stoneweb.com e-mail: sah8nrc. gov William Henries Drew Holland l Acting Director of Engineering Project Manager l Maine Yankee Atomic Power Company GPU Nuclear r1 Old Ferry Road P.O. Box 388 Wascasset. ME 04578 Forked River, NJ 08215 phone: (207) 882 4510 phone: (609)971 4414 fax: (207) 882 5313 e mail: dhollandsgpu.com e mail: henries &myape.com Michael E. Holzmann James S. Hobbs Project Manager Director, Marketing Wisconsin Electric Power Company BNFL Fuel Services Point Beach Nuclear Power Plant Suite 200 6590 Nuclear Road 1 Victor Square Two Rivers, WI 54241 Scotts Valley, CA 95066 phone: (920) 755-6831 phone: (831)438-6444 fax: (920) 755-7430 fax: (831)438-5206 e mail: we3520&wepco.com e mail: jjmhebbsgeompuserve.com Christen L. Howard Senior Engineer Southern Nuclear Operating Company P.O. Box 1295 Birmingham. AL 35201 phone: (205)992 5564 fax: (205) 992 0362 e mail: christen.l.howard3southerneo.com 5

Allen Howe Thomas A. Jones Senior Nuclear Engineer Director of European Nuclear Projects U.S. Nuclear Regulatory Commission ABB Combustion Engineering Nuclear Power MS OWFN 0-6 F18 2000 Day Hill Road Washington, DC 20555 Windsor, CT 06095-1521 phone: (301)415 3561 phone: (860) 285 5257 fax: (301)415 8555 fax: (860)285 3564 e mail: aghl@nrc. gov John H. Eessler John J. Hughes Manager, Spent Fuel and HLW Civil Engineer .

Disposal Program Tennessee Valley Authority EPRI 1101 Market Street 3412 Hillview Avenue LP 4T Palo Alto, CA 943041395 Chattanooga. TN 37402 phone: (650) 855 2069 phone: (423) 751 8055 fax: (650) 855 7945 fax: (423) 751 8314 e-mail: jjhughes@tva. gov Dennis Kierpa Lead Engineer, Surveillance Donald L. Hutson GPU Nuclear Senior Project Manager, One Upper Pond Road Nuclear Fuel Parsippany, NJ 07854 Tennessee Valley Authority phone: (973) 316-7302 1101 Market Street. BR3F fax: (973) 316 7920 Chattanooga, TN 37402 2801 e mail: dkierpaggpu.com phone: (423) 751 4759 fax: (423) 751 4759 Timothy J. Eobetz e mail: dlhutsongtva. gov Project Manger U.S. Nuclear Regulatory Commission Andrea Jennetta 11555 Rockville Pike Pohey Analyst Rockville. MD 20852 Washington Nuclear Corporation phone: (301) 415-8538 Suite 111 fax: (301)415-8555 4600 North Park Avenue Chen Chase, MD 20815 Lawrence Kokajko phone: (301) 652 9500 Technical Assistant fax: (301) 654-1200 U.S. Nuclear Regulatory Commission e mail: aj@nynco.com OWFN-6-F 18 Washington. DC 20555 David C. Jones phone: (30f) 4151309 Lead Engineer, Spent Fuel Management fax: (301)415 8555 Duke Power Company e mail: lek @nrc. gov P.O. Box 1006, M/C ECO8F Charlotte, NC.28201 Michael A. Lalor phone: (704) 382 4080 Licensing l fax: (704) 382 7852 BNFL e mail: dejonesiduke energy.com One Victor Square Scotts Valley, CA 95066 phone: (831) 438 6444 fax: (831)438 5206 e mail: malalorinetscape. net 6

o______ __ __ _ __ _ _ _

l , 1

( Philip M. Lang Senior Quality Engineer Pacific Gas and Electric Company 129 Soltner Drive Chris Lloyd Group Manager, Vendor Quality Assurance Duke Engineering & Senices 580 Main Street -

Kennett Square PA 19348 Bolton, MA 01740 phonei (610) 3471206 phone: (978) 568-2116 fax: (610) 347 1205 fax: (978) 568 3704 e mail: paesblksaol.com e mail: cmilloyd&dukeengineering.com i David L. Larkin Carl F. Lyon Nuclear Fuel Program Manager Project Manager Washington Public Power Supply System U.S. Nuclear Regulatory Commission Mail Drop PE 23 11555 Rockville Pike P.O. Box 968 MS 0-13D18 Richland, WA 99352-0968 Rockville, MD 20852 phone: (509) 377 4201 phone: (301) 415-2296 fax: (509) 377-4099 fax: (301) 415-3061 e mail: dllarkin@wnp2.com e mail: cf1@nre. gov Willington J. Lee Albert J. Machiels Vice President, Engineering and Chief Engineer Progrr.m Manager NAC International EPRI Suite 200 P.O. Box 10412 655 Engineering Drive Palo Alto, CA 94304 Norcross, GA 30092 phone: (650) 855 2054 phone: (770) 447 1144 fax: (650) 855-7945 fax: (770) 447 1797 e mail: amachiel@epri.com e-mail: bill lee @nacintl.com

Ramtin T. Mahini Henry W. Lee Manager Senior Structural Engineer EPRI

-U.S. Nuclear Regulatory Commission 3412 Hillview Avenue M/S 06G22 Palo Alto, CA 94303 Washington, DC 20555 phone: (650) 855-2543 phone: (301)415 8533 fax: (650) 855 1026 fax: (301) 415-8555 e mail: rmahini@epri.com e-mail: hwl@nre. gov Thomas Matula Eric J. Leeds Safet3 Inspection Engineer Section Chief U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 11555 Rockville Pike One White Flint North Rockville, MD 20852 l 11555 Rockville Pike phone: (301) 415-8563 1 Rockville, MD 20852 fax: (301) 415 8555 i l

phone: (301)415 8540 e mail: tom 1&nrc. gov '

fax: (301) 415-8555 I

d William J. McConaghy Tara Neider Vice President, Western U.S. Operations Vice President NAC International Transnuclear. Inc.

Suite 430 Four Skyhne Drive 226 Airport Parkway Hawthorne, NY 10532 San Jose, CA 95110 phone: (914)347 2345 phone: (408) 453-3900 fax: (914) 347 2346 fax: (408)453 3950 e mail: tara.neider@transnuclear.com e mail: bmcconag@nacintl.com Alan P. Nelson Timothy McGinty Senior Project Manager, Plant Support Project Manager Nuclear Energy Institute l

U.S. Nuclear Regulatory Commission . Suite 400 Mail Stop: 0-6-F-18 1776 I Street. N.W.

Washmgton, DC 20555 Washington, DC 20006 3708 l phone: (301) 415-8580 phone: (202) 739-8110 l fax: (301)415 8555 fax: (202) 785-1898 e mail: tjm1@nrc. gov e mail: apntnei.org j I

Stanley Miller Richard J. Netsel ,

Project Manager. Spent Fuel Project Manager Vermont Yankee Nuclear Power Corporation Sargent & Lundy

%0 Main Street 23rd Floor Bolton. MA 01740 55 East Monroe Street phone: (978)568 2320 Chicago, IL 60603 1ax; (978) 568-3732 phone: (312) 269 7103 e mail: stan. miller @vynpc.com fax: (312)269 2617 e mail: richard.j.netzel@slehicago.infonet.com Richard L. Miller General Manager of D&D Robert E. Nickell Bechtel Power Corporation Consultant 0 Amity Court ANATECH Corporation 1:ockville. MD 20855 5435 Oberlin Drive phone: (301) 228 7070 San Diego, CA 92121 fax: (301) 846 9993 phone: (619) 485-9024 e mail: rimiller$bechtel.com fax: (619)485 9024 e mail: rnickellshome.com Thomas Morello, Jr.

Senior Engmeer C.W. Nilsen Baltimore Gas and Electric Company Senior Chemical Engineer j 1650 Calvert Cliffs Parkway U.S. Nuclear Regulatory Commission !

Lusby, MD 20657 Mail Stop T9E43 )

phone: (410)495-4018 Washington, DC 20555 0001 {

fax: (410)495 4498 phone: (301) 415-6209 1 e mmil: thomas.morello@bge.com fax: (301) 415 5385 e mail: cwn%nrc. gov Dasid L. Morse Quahty I.ead Consumers Energy 27780 Blue Star Memorial Highway Covert. MI 49043 phone: (616) 764 2451 fax: (616) 764 3200 e mail: dimorse@cmsenergy.com 8

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Stephen O'Connor Charles W. Pennington Group Senior Vice President,

(. Project hianager U.S. Nuclear Regulatory Commission Engineering and Design Services h1S 06 F18 NAC International Washington, DC 20555 Suite 200 phone: (301) 415-8561 655 Engineering Drive fax: (301)415 8555 Norcross. GA 30092 e mail: sco@nrc. gov phone: (770) 447-1144 fax: (770)447 9746 P. D. Osborne e mail: cpenningtongnacintl,com Civil Engineering hianager Tennessee Valley Authority Holger Pfeifer P.O. Box 2000 hianager, Nuclear Analysis

'O PS 3 NAC International Soddy Daisy, TN 37379 2000 Suite 200 phone: (423) 843 8337 655 Engineering Drive fax: (423)843 8925 Norcross, GA 30092 e mail: pdosborne@tva. gov phone: (770) 447-1144 fax: (770)447 1797 Carmelo Palacios e mail: hpfeifer@nacintl.com hlarketmg and Sales hianager Equipos Nucleares. S.A. Jerry L. Phillabaum -

4 Velazquez.130 Blq.I 3 Engineer 28006 hiadrid PECO Energy Company Spain 965 Chesterbrook Boulevard phone: 01134915631112 Wayne, PA 19087 fax: 01134915640640 phone: (610) 640-6785 e mail: palacios.carmelo@ensa.es fax: (610) 640 6773 e mail: jphillabaum8peco-energy.com Ron Parkhill 1 Senior h!echanical Engineer Kenneth A. Phy i U.S. Nuclear Regulatory Commission Senior Project hianager One White Flint North New York Power Authority 1 l

11555 Rockville Pike James A. FitzPatrick Nuclear Power Plant Rockville, hiD 20852 P.O. Box 41 phone: (301)415 1376 Lycoming, NY 13093-0041 fax: (301) 415 8555 phone: (315) 349-6967 e mail: rwp%nrc. gov fax: (315) 349 6148 e mail: phy.k%nypa. gov Bruce H. Patton Project hianager Paul J. Plante Pacific Gas and Electric Company Project hianager Diablo Canyon Power Plant blaine Yankee Atomic Power Company P.O. Box 56 321 Old Ferry Road Avila Beach, CA 93424 Wiseasset. hie 04578 phone: (805) 545 4809 phone: (207) 882 5806 fax: (805) 545-6992 fax: (207) 882 5313 e mail: bhplspge.com e-mail: plante@myspc.com 9

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I Markus Popa Nicki G. Rocco Department of Energy Special Events Manager ,

1000 Independence Avenue, SW Nuclear Energy Institute Washington.DC 20585 Suite 400 phone: (202) 586 5330 1776 I Street. N.W.

Washington. DC 20006-3708 fax: (202) 586-1047 e mail: markus.popa%rw. doe. gov phone: (202) 739 8014 fax: (202) 872 0560 Chester Posiusny e mail: ngr@nei.org Project Manager U.S. Nuclear Regulatory Commission Harry P. Salmon, Jr.

Vice President, Nuclear Engineering 11555 Rockville Pike Rockville, MD 20852 and Project Control New York Power Authority phone: (301)415 1341 fax: (301) 415-8555 123 Main Street White Plains, hT 10601 phone: (914)287 3812 Dan Prochnow Nuclear Engineer, Project Manager fax: (914)681-6450 Scientech,Inc. e mail: salmon.h@nypa. gov 910 Clopper Road Gaithersburg. MD 20878 Christian Sanna Project Engineering Administration phone: (301) 258 1870 fax: (301) 258 2510 ASME International e mail: prochnow@scientech.com Three Park Avenue New York, hT 10016 Joseph Y.R. Rashid phone: (212)591 8513 Chairman fax: (212) 591 8501 ANATECH Corporation e mail: sannso8asme.org 5435 Oberlin Drive San Diego, CA 92121 Peter H. Seidel Project Manager phone: (619) 455-6350 Stone & Webster Engineering Corporation fax: (619)455 1094 e mail: joe %anatech.com 245 Summer Street Boston, MA 02210 phone: (617) 589 5109 Dennis Reid Project Manager fax: (617) 589 1792 U.S. Nuclear Regulatory Commission e mail: peter.seide1@stoneweb.com M/S 06F18 Mark S. Senderling Washington, DC 20555 phone: (301)415 8556 Engineer Department of Energy fax: (301)415 8555 1000 Independence Avenue,SW e mail: dgrinre. gov Washington,DC 20585 Randy T. Robins phone: (202) 586 2279 Senior Staff E'ngineer fax: (202) 586 1047 e mail: mark.senderling@rw. doe. gov Virginia Power 5000 Dominion Boulevard Glen Allen, VA 23060 phone. (804) 273 2252 -

fax: (804) 273 3543 e mail: randy t. robins %vapower.com 10

t Susan F. Shankman Terry W. Sides Deputy Director Senior Licensing Engineer

[- U.S. Nuclear Regulatory Commission Southern Nuclear Operating Company 11555 Rockville Pike Bin B067 MailStop: 06F18 P.O. Box 1295 Rockville, MD 20852 Birmingham. AL 35201 phone: (301)415 8560 phone: (205) 992 5705 fax: (301) 415-8555 fax: (205) 992 6108 e mail: sis %nrc. gov e mail: twsides3southerneo.com Peter Sharp Richard Slaten Project Manager Spent Fuel Quality Engineer Florida Power & Light Company Sacramento Municipal Utility District St. Lucie Nuclear Power Plant 14440 Twin Cities Road 6501 South Ocean Drive Herald, CA 95638 Jensen Beach, FL 34957 phone: (916) 452-3211 phone: (561)467 7647 fax: (916) 748 2244 fax: (561) 467 7556 Howard Smith Joseph Shea Vice President, Quality Project Manager NAC International U.S. Nuclear Regulatory Commission 655 Engineering Drive 11555 Rockville Pike Norcross, GA 30092 Rockville, MD 20852 phone: (770)447 1144 phone: (301)415 1428 fax: (770) 447 0344 fax: (301) 415-8555 e mail: jws1@nrc. gov Robert Sojka Manager, Special Projects Lisa Shell Vermont Yankee Nuclear Power Corporation Engineer P.O. Box 157 Virginia Power Governor Hunt Road Nuclear Analysis and Fuel Vernon, VT 05354 0157 5000 Dominion Boulevard phone: (802)258 5978 Glen Allen. VA 23060 fax: (802) 258 5886 phone: (804)273 3626 e mail: robert.sojka%vynpc.com fax: (804)273 3543 e mail: lisa_shell%vapower.com Ram Srinivasan Manager, Configuration Management Howard S. Shimon BhTL Program Manager One Victor Square Washington Nuclear Corporation Scotts Valley, CA 95066 3132 West Joliet Court - 127N phone: (831) 438-6444 Mequon, WI 53092 2315 fax: (831) 438 5206 phone: (414) 238-4631 e mail: sjeram@hotmail.com fax: (414) 238 4632 e mail: h4nynco.com Christopher P. Srock Vice President of Engineering and Contract Management U.S. Tool & Die, Inc.

200 Braddock Avenue Turtle Creek, PA 15145 phone: (412) 823 3773 x10 fax: (412) 823 6669 e mail: ustd@sgi. net 11

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Thomas J. Szymanski

' David Stueckel Refueling Engineer Technical Analyst Southern California Edison Company Virginia Power San Onofre Nuclear Generating Station 5000 Dominion Boulevard Glen Allen, VA 23060 P.O. Box 128 MS D3B San Clemente, CA 92672 phone: (804)273 3065 phone: (949) 368 6758 fax: (804) 273 3715 e-mail: tom _szymanski@vapower.com fax: - ($49) 368 9007 e mail: Eteechda@ songs.see.com David T. Tang Senior Structural Engineer Joseph Dringer U.S. Nuclear Regulatory Commission Engineering Manager Duke Engineering & Services Mail Stop: 0-6F 18 400 South Tryon Street Washington. DC 20555 Charlotte, NC 28201 phone: (301)415-8535 phone: (704) 382 5711 fax: (301)415-8555 fax: (704) 382 8666 e mail: dtt$nrc.com e mail: jbstringer$dukeengineering.com Getachew Tesfaye Senior Engineer Fritz Sturz Baltimore Gas and Electne Company Section Chief, Technical Review Section U.S. Nuclear Regulatory Commission Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Spent Fuel Project Office Lusby, MD 20657 MS 06F18 Washington, DC 2C555 phone: (410)495 3736 phone: (301) 415 8530 fax: (410)495 2067 e mail: getachew.tesfaye4bge.com fax: (301)415 8555 .

e mail: fesEnre. gov Thomas C. Thompson Eileen M. Supko Director, Licensing and Competitive Senior Consultant Assessment Energ3 ResourcesInternational,Inc. NAC International Suite 650 Suite 200 655 Engineering Drive 1015 2 8th Street. N.W.

Norcross, GA 30092 Washington, DC 20036 phone: (202) 785 8833 phone: (770) 447 1144 fax: (202)785 8834 fax: (770)447 1797 e mail: supko@energyresources.com e mail: tthompsongnacintl.com William L. Swant David Tiktinsky Project Manager Project Manager U.S. Nuclear Regulatory Commission Nebraska Public Power District 141415th Street MS 0 6 F 18 Columbus, NE 68601 Washington. DC 20555 phone: (402b563 5354 phone: (301) 415-8523 fax: fax: (301)415 8555 (402) 563 5838 e mail: wiswantz@nppd.com e-mail: dht43rc. gov 12

1 1

a Leonard A.Trernblay Jay T. Wileman 1 Yankee ISFSI Project Manager Manager, Business Development

(' . Duke Engineering & Services GE Nuclear Energy 580 Main Street P.O. Box 780 Bolton, MA 01740 M/C A20 phone: (978) 568 2383 Wilmington, NC 28402 fax: (978) S68 3735 phone: (910)675-6625 e mail: latremblgdukeencineering.com fax: (910) 675-661) e mail: jay.wileman% gene.ge.com George E. Vaughan Vice President, U.S. Sales H. Lee Williams NAC International Senior Manager of Projects 655 Engineering Drive Tennessee Valley Authority Norcross, GA 30092 P.O. Box 2000 phone: (770)447 1144 PAB1-C fax: (770)447 1797 Decatur, AL 35609 e mail: gvaughangnacintl.com phone: (256)729-3123 fax: (256) 729-2606 John A. Vincent e mail: hlwilliams@tva. gov Senior Engineer, Nuclear Fuel GPU Nuclear, Inc. Carl J. Withee One Upper Pond Road Senior Criticality and Shielding Engineer Parsippany. NJ 070541096 U.S. Nuclear Regulatory Commission phone: (973) 316-7289 Mail Stop: 0-6-F18 fax: (610) 607 8330 Washir.gton, DC 20555 e mail: jvincent@gpu.com phone: (301) 415-8534 fax: (301) 415-8555 Jerry L. Watts e mail: cjw@nrc. gov Licensing Engineer Tennessee Valley Authority Gregory C.Withrow P.O. Box 2000 Engineering Manager Soddy Daisy. TN 37379 Consumers Energy phone: (423) 843 7271 10269 US 31 North fax: (423) 843 8750 Charlevoix. MI 49720 e mail: jlwattrritva. gov phone: (616) 547 8176 fax: (616) 547 8246 Paul D. Watts Manage: of Quality Audits Brian Wohlers and Staff Services Project Manager RANOR, INC. Alliant Energy P.O. Box 458 Duane Arnold Energy Center Westminster, MA 01475 3277 DAEC Road i phone: (978) 874 0591 Palo,IA 52324 fax: (978)874 2748 phone: (319) 851 7400 e mail: pwatts%ranor.com fax: (319) 851 7285 e mail: brianwohlers%alliant-energy.com 13

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s Howard J. Wong Director. Qu:W.ty Assurance ;

BNFL One Victor Square -

Scotts Valley, CA 95066 phone: (408)430-3210 fax: (408)438 5206 e . nail: hjwong224hotmail.com Michael Yaksh Manager, Thermal and Structural Analysis NAC International Suite 200 655 Engineering Drive Norcross, GA 30092 phone: (770) 447 1144 fax: (770)447 1797 e mail: myakshEnacintl.com Francis Young Senior Project Manager -

U.S. Nuclear Regulatory Commission 11555 Rockr Je Pike Rockville, MD 20852 phone: (301)415 3207 fax: (301)415-8555 e mail: fay &nrc. gov George Alan Zinke Director, Regulatory Affairs Maine Yankee Atomic Power Company 321 Old Ferry Road Wiscasset, ME 04578-4922 phone: (207)882 5824 f fax: (207)882 5773 e mail: zinkeggmyspc.com Gerard P. van Noc-dennen f Regulatory Affairs hianager Connecticut Yankee Atomic Power Company 362 Injun Hollow Road East Hampton, CT 06424-3099 l

phone: (860)267 3938 fax: (860)2,67 3937 e mail: vannogpEgwsmtp.nu.com 14

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