Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems

Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems

ML031060284
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 07201004, 07201007, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant
Issue date:	06/07/1995
From:	Cool D, Grimes B NRC/NMSS/IMNS, Office of Nuclear Reactor Regulation
To:
References
IN-95-029, NUDOCS 9506050138
Download: ML031060284 (11)

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS

WASHINGTON, D.C. 20555-0001 June 7, 1995 NRC INFORMATION NOTICE 95-29: OVERSIGHT OF DESIGN AND FABRICATION ACTIVITIES

FOR METAL COMPONENTS USED IN SPENT FUEL DRY

STORAGE SYSTEMS

Addresse

All holders of operating licenses or construction permits for nuclear power

reactors.

Independent spent fuel storage installation designers and fabricators.

,

Purpose

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

alert addressees to observed shortcomings in oversight of design and

fabrication activities for metal components used in spent fuel dry storage

systems. It is expected that recipients will review the information for

applicability to their facilities and consider actions, as appropriate, to

avoid similar problems. However, suggestions contained in this information

notice are not NRC requirements; therefore, no specific action or written

response is required.

Description of Circumstances

As part of an application for an independent spent fuel storage installation

license or spent fuel dry storage system certificate of compliance, the

applicant provides quality assurance commitments to NRC pursuant to the

requirements of Part 72, Subpart G, of Title 10 of the Code of Federal

Regulations. The holder of a general license under 10 CFR Part 72, Subpart K,

must implement the quality assurance program approved by NRC under its 10 CFR

Part 50 license for activities under the general license. NRC performs

inspections of licensees and certificate of compliance holders to verify

adequate implementation of these regulatory requirements.

NRC has been conducting quality assurance inspections of designers and

fabricators of metal components for dry storage systems since 1991. Metal

components of dry storage systems are normally fabricated at vendor facilities

located offsite from a power reactor licensee. These components include items

(e.g., storage canister, storage basket, and onsite transfer cask) that are

not part of the concrete installation structures. Inspections have been

conducted at design facilities, fabrication facilities and reactor licensee

sites to review specific dry storage system quality requirements and their

implementation. A total of six NRC inspection reports have been issued to

date: specifically, Inspection Report Nos. 722501/91-02, 721007/92-01,

721004/93-07, 72-1007/94-207, 72-0010/94-210, and 72-0010/94-212. The results

9506050138 PDR f4E c sa 50Qs:x

O1R -'s'

Lisp 9I

IN 95-29 June 7, 1995 of these inspections are relevant to licensees and certificate holders who are

currently, or are planning to be, involved in design, fabrication or oversight

activities associated with dry storage systems. In five of the six

inspections, NRC identified shortcomings in the implementation of quality

assurance commitments. The most frequent Inspection findings are categorized

in Attachment 1, mInspection Findings for Design and Fabrication Activities of

Metal Components Used in Spent Fuel Dry Storage Systems.*

Discussion

NRC inspects the implementation of licensee and certificate holder quality

assurance programs to verify the quality of metal components used in dry

storage systems. In order to ascertain compliance with safety analysis report

commitments, the inspection teams review design and fabrication records, weldment radiographs, licensee oversight of vendor activities, fabrication

processes, nondestructive examination activities, and personnel

qualifications.

As shown in Attachment 1, the majority of inspection findings were in the

areas of document control, quality assurance records, and control of purchased

material, equipment and services.

These inspection results present a number of findings which individually may

not be of high safety significance. However, when the inspection team

identifies many occurrences of the same type of finding, or many findings in a

variety of areas, the overall assurance of quality is undermined. On several

occasions, the quality of safety-related hardware was indeterminate at the

conclusion of the inspection. Only after extensive searches for missing

quality records, physical reexamination or testing were the issues resolved.

The time required to resolve these inspection findings has resulted in

significant delays in schedules to reactor facility licensees and certificate

holders.

Related Generic Communications

IN 95-28, uEmplacement of Support Pads for Spent Fuel Dry Storage

Installations at Reactor Sites."

KJ

IN 95-29 June 7, 1995 This Information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical con cts listed below.

-

Brian K. Grimes, Director Donald A. Cool, Director

Division of Project Support Division of Industrial and

Office of Nuclear Medical Nuclear Safety

Reactor Regulation Office of Nuclear Material

Safety and Safeguards

Technical contacts: Stephen C. O'Connor, NMSS

(301) 415-7878 Stephen S. Koenick, NRR

(301) 415-2841 Attachments:

1. Inspection Findings for Design and Fabrication

Activities of Metal Components Used in

4-44 % L y 4 Spent Fuel Dry Storage Systems

2. List of Recently Issued NMSS Information Notices

3. List of Recently Issued NRC Information Notices

Attachment 1 IN 95-29 June 7, 1995 INSPECTION FINDINGS FOR DESIGN AND FABRICATION ACTIVITIES

OF METAL COMPONENTS USED IN SPENT FUEL DRY STORAGE SYSTEMS

Quality Assurance (QA) No. of

Program Section Inspection

Findings

Document Control 20

Maintenance of QA Records 19 Control of Purchased Material, Equipment, and Services 18 Control of Measuring and Test Equipment 16 Instructions, Procedures, and Drawings 14 Inspection (Fabrication Hold Points and Quality Control) 12 Nonconforming Materials, Parts, or Components 11 Description of QA Program Findings:

• Document control deficiencies can be summarized generally as outdated

revisions of procedures, instructions and drawings located where they

may be used inadvertently by personnel, or missing authorization

signatures, dates or approval stamps.

• Maintenance of QA records deficiencies can be summarized generally as

inadequacies in maintaining sufficient documented evidence of welder

qualifications, dimensional checks, certified material test reports, or

records of weld repairs.

• Control of purchased material, equipment, and services deficiencies can

be summarized generally as use of contractors or suppliers not on an

approved vendor list,, missed periodic audits of contractors or suppliers

on an approved vendor list, or inadequate examination of products on

delivery.

• Control of measuring and test equipment deficiencies can be summarized

generally as use of inappropriate or uncalibrated equipment in

fabrication, test or operation activities.

• Deficiencies in instructions, procedures and drawings can be summarized

generally as performing activities affecting quality that are not in

accordance with approved documented guidelines.

• Inspection deficiencies can be summarized generally as fabrication hold

points not witnessed and approved by authorized personnel, or

unqualified quality control inspection personnel.

• Nonconforming materials, parts or components deficiencies can be

summarized generally as nonconforming items not identified as such to

prevent inadvertent use, or not tracked and documented properly to

maintain a complete history of materials used in fabrication.

P .I  ;

Attachment 2 IN 95-29 June 7, 1995 Page I of 1 LIST OF RECENTLY ISSUED

NMSS INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

95-28 Emplacement of Support 06/05/95 All holders of OLs or CPs

Pads for Spent Fuel Dry for nuclear power reactors.

Storage Installations at

Reactor Sites

95-25 Valve Failure during 05/11/95 All U.S. Nuclear Regulatory

Patient Treatment with Commission Medical

Gamma Stereotactic Licensees.

Radiosurgery Unit

94-64, Reactivity Insertion Trans- 04/06/95 All holders of OLs or CPs

Supp. I ient and Accident Limits for Nuclear Power Reactors

for High Burnup Fuel and all fuel fabrication

licensees.

95-07 Radiopharmaceutical Vial 01/27/95 All U.S. Nuclear Regulatory

Breakage during Preparation Commission medical licensees

authorized to use byproduct

material for diagnostic

procedures.

95-01 DOT Safety Advisory: 01/04/95 All U.S. Nuclear Regulatory

High Pressure Aluminum Commission licensees.

Seamless and Aluminum

Composite Hoop-Wrapped

Cylinders

94-89 Equipment Failures at 12/28/94 All U.S. Nuclear Regulatory

Irradiator Facilities Commission irradiator

licensees.

89-25, Unauthorized Transfer of 12/07/94 All fuel cycle and material

Rev. 1 Ownership or Control of licensees.

Licensed Activities

94-81 Accuracy of Bioassay 11/25/94 All U.S. Nuclear Regulatory

and Environmental Commission licensees.

Sampling Results

Attachment 3 IN 95-29 June 7. 1995 Page I of 1 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

95-28 Emplacement of Support 06/05/95 All holders of OLs or CPs

Pads for Spent Fuel Dry for nuclear power reactors.

Storage Installations at

Reactor Sites

95-27 NRC Review of Nuclear 05/31/95 All holders of OLs or CPs

Energy Institute, for nuclear power plants.

wThermo-Lag 330-1 Combustibility Evaluation

Methodology Plant Screening

Guide'

95-26 Defect in Safety- 05/31/95 All holders of OLs or CPs

Related Pump Parts due for nuclear power reactors.

to Inadequate Heat

Treatment

94-61, Corrosion of William 05/25/95 All holders of OLs or CPs

Supp. 1 Power Gate Valve Disc for nuclear power reactors.

Holders

95-25 Valve Failure during 05/11/95 All U.S. Nuclear Regulatory

Patient Treatment with Commission Medical

Gamma Stereotactic Licensees.

Radiosurgery Unit

95-24 Summary of Licensed 04/25/95 All holders of OLs or CPs

Operator Requalification for nuclear power reactors.

Inspection Program

Findings

95-23 Control Room Staffing 04/24/95 All holders of OLs or CPs

Below Minimum Regulatory for nuclear power reactors

Requirements and all licensed operators

and senior operators at

those reactors.

95-22 Hardened or Contaminated 04/21/95 Al I holders of OLs or CPs

Lubricants Cause Metal for nuclear power reactors.

Clad Circuit Breaker

Failures

OL - Operating License

CP - Construction Permit

~' IN 95-29 June 7, 1995 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below.

orig /s/'d by BKGrimes orig /s/'d by DACool

Brian K. Grimes, Director Donald A. Cool, Director

Division of Project Support Division of Industrial and

Office of Nuclear Medical Nuclear Safety

Reactor Regulation Office of Nuclear Material

Safety and Safeguards

Technical contacts: Stepheri C. O'Connor, NMSS

(301) 4415-7878 Stephen S. Koenick, NRR

(301) 415-2841 Attachments:

1. Inspection Findings for Design and Fabrication

Activities of Metal Components Used in

Spent Fuel Dry Storage Systems

2. List of Recently Issued NMSS Information Notices

3. List of Recently Issued NRC Information Notices

DOCUMENT NAME: 95-29. IN

• See previous concurrence

To Becalwm s cam at this document. hdlicate In the box: 'C'

• CoDy without aettchmentlenclosure FE - Copy with Mttachment/enclosurm ENS No copy

OFFICE OECB/DOPS ADM:PUB C:EMEB/DE D:DOT PD3-III

NAME SSKoenick* Tech Ed* GBagchi* RSpessard* GHMarcus*

DATE 05/ /95 05/19/95 05/23/95 05/23/95 05/25/95 t7 1 OFFICE SC:OECB/DOPS OECB/DOPS [D:IHff0 L C:OECB/DOPS l

NAME EFGoodwin* RJKiessel* DI Sgol___--- AEChaffee*

DATE 105/25/95 02597/ '/95 05/26/95 _____/95 OFFICIAL RECORD COPY

1- '-.' IN 95-XX

May XX, 1995 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below.

Brian K. Grimes, Director Donald A. Cool, Director

Division of Project Support Division of Industrial and

Office of Nuclear Medical Nuclear Safety

Reactor Regulation Office of Nuclear Material

Safety and Safeguards

Technical contacts: Stephen C. O'Connor, NMSS

(301) 415-7878 Stephen S. Koenick, NRR

(301) 415-2841 Attachments:

1. Inspection Findings for Design and Fabrication

Activities of Metal Components Used in

Dry Spent Fuel Storage Systems

2. List of Recently Issued NRC Information Notices

DOCUMENT NAME: G:\SCO\INFO.2

• See previous concurrence

E' - Copy with attachment/enclosure N = No copy

document, Indicate hIthe box: IC - Copy without attachment/enclosure

To rece"ve a copy of this

OFFICE OECB/DOPS I ADM:PUB l C:EMEB/DE D:DOTS l PD3-III

NAME SSKoenick* Tech Ed* GBagchi* RSpessard* GHMarcus*

DATE 05/ /95 0 905/23/95 05/23/95 05/25/95 OFFICE SC:OECB/DOPS I OECB/DOPS ID:IMNS/NMSS C:OECB/DOPS D:DOPS/NRR

NAME EFGoodwin* RJKiessel* DACool AEChaffee* BKG I

DATE 5/25/95 0 5 5 1051 /95 05/26/95 05/ /95 1

_ OFFICIAL RECORD COPY

b az4/ jso

1 i-' IN 95-XX

May XX, 1995 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below.

Brian K. Grimes, Director Donald A. Cool, Director

Division of Project Support Division of Industrial and

Office of Nuclear Medical Nuclear Safety

Reactor Regulation Office of Nuclear Material

Safety and Safeguards

Technical contacts: Stephe n C. O'Connor, NMSS

(301) 415-7878 S. Koenick, NRR

(301) 415-2841 Attachments:

1. Inspection Findings for Design and Fabrication

Activities for Dry Spent Fuel Storage

Metal Components

2. List of Recently Issued NMSS Information Notices

3. List of Recently Issued NRR Information Notices

DOCUMENT NAME: G:\SSK2\ISFSIQA.IN

• See previous concurrence

E' = Copy with attachmentlenclosure 'N' - No copy

To receive a copy of this document, Indicate In the box: 'C = Copy without attachment/.nclosure

ADM:PUB C:EMEB/DE D:DOTS PD3-III

OFFICE IOECB/DOPS

5SKoenick* Tech Ed* GBagchi* RSpessard* GHMarcus*

NAME

05/ /95 05/19/95 05/23/95 05/23/95 05/25/95 DATE

OFFICE SC:OECB/DOPS OECB/DOPS D:IMNS/NMSS [

C:OECB/DOPS D:DOPS/NR

EFGoodwin* RJKiessel* DCool IAEChaffee* BKGrimes

NAME

DATE 05/25/95 05/25/95 05/ /95 105/26/95 05/ /95 OFFICIAL RECORD COPY

\"-/ IN 95-XX

May XX, 1995 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below.

Brian K. Grimes, Director Donald A. Cool, Director

Division of Project Support Division of Industrial and

Office of Nuclear Medical Nuclear Safety

Reactor Regulation Office of Nuclear Material

Safety and Safeguards

Technical contacts: Stephen C. O'Connor, NMSS

301/415-7878 S. Koenick, NRR

301/415-2841 Attachments: 1) Inspection Findings

2) List of Recently Issued NRC Information Notices

DOCUMENT NAME: G:\SSK2\ISFSIQA.I N

To receive a copy of this docummnt, indicate iinthe box: "C" = Copy without attachment/enclosure "E" = Copy with

at taY~a s }IaI -... r. HullN bin

lnn

OFFICE OECB/DOPS TECH ED* C:EMEB/DE D:DOTS PD3-III

NAME SSKoenick* GBagchi* RSpessard* GHMarcus*

DATE 05/ /95 05/ /95 05/ /95 05/ /95 05/ /95 OFFICE SC:OECB/DOPS l OECB/DOPS L D:IMNS/NMSS I IC: S D:DOPS/NRR

NAME EFGoodwin* RJKiessel* DCool AE eAffe

m BKGrimes

DATE 105/ /95 05/ /95 05/ /95 105/ 2/95 05/ /95

• See previous concurrence

I I IN 95-XX

May XX, 1995 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below.

Brian K. Grimes, Director Donald A. Cool, Director

Division of Project Support Division of Industrial and

Office of Nuclear Medical Nuclear Safety

Reactor Regulation Office of Nuclear Material

Safety and Safeguards

Technical contacts: Stephen C. O'Connor, NMSS

301/415-7878 S. Koenick, NRR

301/415-2841 Attachment:

List of Recently Issued NRC Information Notices

DOCUMENT NAME:

attachment/enclosure

OFFICE

G:\SSK2\ISFSIQA. I N

To receive a copy of this document, indicate finthe box:

"I" = No copy

jOTECH ED

"C" = Copy without attachment/encLosure

C /DE

"El' z Copy with

PD3-II

Jlk, NAME SSKoenick 5 r"Q"

t pnu lRSpe i rd GHMarcus.

DATE 05/14/95 05/1T/9595 05/ e/9 5/;,/79 5

095 OFFICE SC:OECB/DOPSI OECB/DOPS fD:IMNS/NMSS C:OECB/DOPS D:D0PS/NRRS

NAME EFGoodwiX n &9 WRJKiessel D

DCool AEChaffee BKGrimes

DATE 05/2sl95 05/ 95 05/ /95 05/ /95 05/ /95