Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems: Difference between revisions
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{{#Wiki_filter:UNITED STATES | {{#Wiki_filter:UNITED STATES | ||
COMMISSION | NUCLEAR REGULATORY COMMISSION | ||
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS | |||
NOTICE 95-29: OVERSIGHT | 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== | ==Purpose== | ||
The U.S. Nuclear Regulatory | 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 | |||
to | applicability to their facilities and consider actions, as appropriate, to | ||
in | avoid similar problems. However, suggestions contained in this information | ||
notice are not NRC requirements; therefore, no specific action or written | |||
response is required. | |||
for | ==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 | |||
of | 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 | |||
and | 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 | |||
of | 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. | |||
of | As shown in Attachment 1, the majority of inspection findings were in the | ||
and | 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 | |||
of | 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 | |||
of | 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 | 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 | |||
of | revisions of procedures, instructions and drawings located where they | ||
may be used inadvertently by personnel, or missing authorization | |||
signatures, dates or approval stamps. | |||
of | * 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 | |||
activities | 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 | |||
and | 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 | |||
1 | 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 | |||
of | 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 | |||
of | 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 | |||
of | 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. | |||
or | 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 | |||
and | 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 | |||
2 | |||
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 | *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. | |||
D:D0PS/NRRS | 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 | NAME EFGoodwiX n &9 WRJKiessel D | ||
DCool AEChaffee BKGrimes | |||
DATE 05/2sl95 05/ 95 05/ /95 05/ /95 05/ /95}} | |||
{{Information notice-Nav}} | {{Information notice-Nav}} |
Latest revision as of 04:32, 24 November 2019
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
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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
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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
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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
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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
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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:
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G:\SSK2\ISFSIQA. I N
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jOTECH ED
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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
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DATE 05/2sl95 05/ 95 05/ /95 05/ /95 05/ /95