Information Notice 1985-40, Deficiencies in Equipment Qualification Testing and Certification Process: Difference between revisions
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{{#Wiki_filter:SSINS No.: 6835 IN 85-40 UNITED STATES | {{#Wiki_filter:SSINS No.: 6835 IN 85-40 | ||
UNITED STATES | |||
COMMISSION | NUCLEAR REGULATORY COMMISSION | ||
OFFICE OF INSPECTION | OFFICE OF INSPECTION AND ENFORCEMENT | ||
WASHINGTON, D.C. 20555 May 22, 1985 IE INFORMATION NOTICE NO. 85-40: DEFICIENCIES IN EQUIPMENT QUALIFICATION | |||
WASHINGTON, D.C. 20555 May 22, 1985 IE INFORMATION | |||
TESTING AND CERTIFICATION PROCESS | |||
TESTING AND CERTIFICATION | |||
PROCESS | |||
==Addressees== | ==Addressees== | ||
: | : | ||
license (OL) or a construction | |||
license (OL) or a construction | |||
===All holders of a nuclear power reactor operating=== | |||
permit (CP). | permit (CP). | ||
==Purpose== | ==Purpose== | ||
: | : | ||
that quality-related deficiencies | |||
notice is to alert | This information notice is to alert licenseesapproval, and certification process | ||
in the qualification documentation, review, Branch (VPB) of the NRC during its | |||
have been identified by the Vendor Programobservations suggest that some vendor | |||
review of qualification activities. NRC not provide a sufficient basis for | |||
qualification activities and practices may | |||
qualification certification. | |||
information for specific and generic | |||
It is suggested that recipients review this supporting environmental qualification | |||
applicability to ensure that documentation is complete. Suggestions | |||
of safety-related equipment at their facilities | |||
NRC requirements; therefore, no | |||
contained in this notice do not constitute | |||
specific action or response is required. | |||
==Description of Circumstances== | |||
: | |||
1, June 1984), and IEEE Standards | |||
10 CFR 50.49, Regulatory Guide 1.89 (Revision information demonstrating qualifi- | |||
323-1974 and 323-1983 each require auditablelicensee management and the NRC that | |||
to | cation to provide continuing assurance to period during which it is installed | ||
equipment in use is qualified for the entire B, provides quality assurance | |||
in the nuclear power plant. 10 CFR 50, Appendix of qualification files. IEEE | |||
requirements for the generation of all elements | |||
Regulatory Guide 1.89), requires that | |||
Standard 323-1974, Section 8 (endorsed by be reviewed and approved by the | |||
individual elements of qualification files inspected vendor qualification | |||
licensee. Since July 1982, the VPB has actively Inspections have been performed | |||
efforts for compliance to these NRC requirements. | |||
testing laboratories, architect-engineers, at manufacturing facilities, independent | |||
and nuclear steam supply system (NSSS) vendors. | |||
examples where more active licensee | |||
NRC observations at the vendor level provideshould have occurred. In some cases, participation in the qualification effort to justify because of documen- certification of qualification is now difficult Some examples of NRC findings | |||
tation and test practices employed by vendors. | |||
follow. | |||
8505200600 | |||
IN 85-40 | |||
May 22, 1985 1. Qualification activities not performed under a QA | |||
10 C 5, Appenx program consistent with | |||
I | |||
o Qualification testing of Class lE equipment | |||
appropriate QA programs. was conducted without | |||
o No QA requirements were imposed on organizations | |||
related services (such as irradiation, providing safety- associated with the qualification process.calibration, and analyses) | |||
2. Qualification test report conclusions not | |||
test data not availab e supported by test data or | |||
o Test profiles shown in qualification reports | |||
during test. were not actually achieved | |||
o Reports identified specimens or materials | |||
those actually tested. that were different from | |||
o Test records showed inadequate sensitivity/resolution | |||
sensitivity/resolution | |||
of test equipment. | of test equipment. | ||
o Documentation | o Documentation required by the standards | ||
required by the standards | |||
was not available (test plans, equipment referenced in the test report | |||
lists, and calibration | lists, and calibration records). | ||
° Test anomalies werenot adequately reported or evaluated. | |||
o Similarity between test specimens and items | |||
established. to be qualified was not | |||
3. Documentation to support the validity of | |||
for lifetime oftheequipment qualification not maintained | |||
o Supporting test data were destroyed after | |||
five years. | |||
4. Inadequate review, approval, or certification | |||
of test results | |||
o Interfaces/responsibilities of organizations | |||
qualification process were not clearly involved in the | |||
defined. | |||
o Test reports contained statements that testing | |||
"guidelines" or "intent" of standards referencedsatisfied the | |||
in the specification. | in the specification. | ||
Detailed descriptions | ===Detailed descriptions of NRC findings and=== | ||
published in NUREG-0040, "Licensee Contractor results of these inspections are | |||
Report," Volumes 6, 7, and 8. This report and Vendor Inspection Status | |||
is | |||
and it can be obtained from the Superintendent published quarterly by the NRC, | |||
Printing Office, Post Office Box 37082, of Documents, U.S. Government | |||
Washington, D.C. 20013-7982. | |||
and | IN 85-40 | ||
May 22, 1985 Correspondence with contractors and vendors relative to the inspection data | |||
contained in NUREG-0040 is placed in the NRC Public Document Room, 1717 H Street, N. W., Washington, D.C. 20555. | |||
Discussion: | |||
The deficiencies described in this notice resulted from the review of a vendor's | |||
qualification activities against the applicable procurement document requirement | |||
of | or, in the case of generic qualification, against the applicable QA criteria. | ||
An overall assessment of identified deficiencies (1) suggests that some vendor | |||
qualification activities may not adequately support the applicable NRC require- ments, and (2) emphasizes the need for increased licensee attention to the adequacy | |||
of their vendor procurement control practices for qualification activities and | |||
and | the definition of responsibilities and interfaces in the qualification process. | ||
Documentation from vendors and test laboratories form the basis for meeting the | |||
equipment qualification requirements of paragraphs (d), (e), (f) and (j) of 10 | |||
CFR 50.49. This documentation may include procurement specifications, test plans, test procedures, test logbooks, qualification test reports, test data, analyses | |||
and corrective action to resolve test anomalies, test configurations and | |||
interfaces, and quality assurance information. | |||
The NRC staff considers the above-identified deficiencies to be representative | |||
examples of problems with vendors and test laboratories providing qualification | |||
services to other vendors and user utilities. Although there may be specific | |||
problems applicable to a particular utility, the staff expects that user | |||
utilities will consider the overall applicability of the above information in | |||
establishing qualification of safety-related equipment. | |||
No specific action or written response is required by this notice. If you have | |||
any questions regarding this notice, please contact the Regional Administrator | |||
of the appropriate NRC regional office or this office. | |||
ar l. orian, Director | |||
Divis n of Emergency Preparedness | |||
and ngineering Response | |||
Office of Inspection and Enforcement | |||
===Technical Contact:=== | |||
===G. T. Hubbard, IE=== | |||
(301) 492-9759 Attachment: List of Recently Issued IE Information Notices | |||
Attachment 1 IN 85-40 | |||
May 22, 1985 LIST OF RECENTLY ISSUED | |||
IE INFORMATION NOTICES | |||
Information Date of | |||
Notice No. Subject Issue Issued to | |||
85-39 Auditability of Electrical 5/22/85 All power reactor | |||
Equipment Qualification facilities holding | |||
Records At Licensees' an OL or CP | |||
Facilities | |||
85-38 Loose Parts Obstruct Control 5/21/85 All PWR facilities | |||
Rod Drive Mechanism designed by B&W | |||
holding an OL or CP | |||
85-37 Chemical Cleaning Of Steam 5/14/85 All pressure water | |||
At Milestone | Generator At Milestone 2 reactor facilities | ||
holding an OL or CP | |||
84-55 Seal Table Leaks At PWRs 5/14/85 All power reactor | |||
Sup. 1 facilities holding | |||
an OL or CP | |||
85-20 Motor-Operated Valve Failures 5/14/85 All power reactor | |||
Sup. 1 Due To Hammering Effect facilities holding | |||
an OL or CP | |||
85-36 Malfunction Of A Dry-Storage, 5/9/85 All licensees | |||
Panoramic, Gamma Exposure possessing gamma | |||
Irradiator irradiators | |||
84-52 Inadequate Material 5/8/85 All power reactor | |||
Sup. 1 Procurement Controls On facilities holding | |||
The Part Of Licensees And an OL or CP | |||
Vendors | |||
85-35 Failure Of Air Check Valves 4/30/85 All power reactor | |||
holding | To Seat facilities holding | ||
an OL or CP | |||
85-34 Heat Tracing Contributes To 4/30/85 All power reactor | |||
Corrosion Failure Of Stainless facilities holding | |||
Steel Piping an OL or CP | |||
84-84 Deficiencies In Ferro- 4/24/85 All power reactor | |||
holding | Rev. 1 Resonant Transformers facilities holding | ||
an OL or CP | |||
License | DL = Operating License | ||
Permit}} | CP = Construction Permit}} | ||
{{Information notice-Nav}} | {{Information notice-Nav}} | ||
Revision as of 02:37, 24 November 2019
SSINS No.: 6835 IN 85-40
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 May 22, 1985 IE INFORMATION NOTICE NO. 85-40: DEFICIENCIES IN EQUIPMENT QUALIFICATION
TESTING AND CERTIFICATION PROCESS
Addressees
license (OL) or a construction
All holders of a nuclear power reactor operating
permit (CP).
Purpose
that quality-related deficiencies
This information notice is to alert licenseesapproval, and certification process
in the qualification documentation, review, Branch (VPB) of the NRC during its
have been identified by the Vendor Programobservations suggest that some vendor
review of qualification activities. NRC not provide a sufficient basis for
qualification activities and practices may
qualification certification.
information for specific and generic
It is suggested that recipients review this supporting environmental qualification
applicability to ensure that documentation is complete. Suggestions
of safety-related equipment at their facilities
NRC requirements; therefore, no
contained in this notice do not constitute
specific action or response is required.
Description of Circumstances
1, June 1984), and IEEE Standards
10 CFR 50.49, Regulatory Guide 1.89 (Revision information demonstrating qualifi-
323-1974 and 323-1983 each require auditablelicensee management and the NRC that
cation to provide continuing assurance to period during which it is installed
equipment in use is qualified for the entire B, provides quality assurance
in the nuclear power plant. 10 CFR 50, Appendix of qualification files. IEEE
requirements for the generation of all elements
Regulatory Guide 1.89), requires that
Standard 323-1974, Section 8 (endorsed by be reviewed and approved by the
individual elements of qualification files inspected vendor qualification
licensee. Since July 1982, the VPB has actively Inspections have been performed
efforts for compliance to these NRC requirements.
testing laboratories, architect-engineers, at manufacturing facilities, independent
and nuclear steam supply system (NSSS) vendors.
examples where more active licensee
NRC observations at the vendor level provideshould have occurred. In some cases, participation in the qualification effort to justify because of documen- certification of qualification is now difficult Some examples of NRC findings
tation and test practices employed by vendors.
follow.
8505200600
May 22, 1985 1. Qualification activities not performed under a QA
10 C 5, Appenx program consistent with
I
o Qualification testing of Class lE equipment
appropriate QA programs. was conducted without
o No QA requirements were imposed on organizations
related services (such as irradiation, providing safety- associated with the qualification process.calibration, and analyses)
2. Qualification test report conclusions not
test data not availab e supported by test data or
o Test profiles shown in qualification reports
during test. were not actually achieved
o Reports identified specimens or materials
those actually tested. that were different from
o Test records showed inadequate sensitivity/resolution
of test equipment.
o Documentation required by the standards
was not available (test plans, equipment referenced in the test report
lists, and calibration records).
° Test anomalies werenot adequately reported or evaluated.
o Similarity between test specimens and items
established. to be qualified was not
3. Documentation to support the validity of
for lifetime oftheequipment qualification not maintained
o Supporting test data were destroyed after
five years.
4. Inadequate review, approval, or certification
of test results
o Interfaces/responsibilities of organizations
qualification process were not clearly involved in the
defined.
o Test reports contained statements that testing
"guidelines" or "intent" of standards referencedsatisfied the
in the specification.
Detailed descriptions of NRC findings and
published in NUREG-0040, "Licensee Contractor results of these inspections are
Report," Volumes 6, 7, and 8. This report and Vendor Inspection Status
is
and it can be obtained from the Superintendent published quarterly by the NRC,
Printing Office, Post Office Box 37082, of Documents, U.S. Government
Washington, D.C. 20013-7982.
May 22, 1985 Correspondence with contractors and vendors relative to the inspection data
contained in NUREG-0040 is placed in the NRC Public Document Room, 1717 H Street, N. W., Washington, D.C. 20555.
Discussion:
The deficiencies described in this notice resulted from the review of a vendor's
qualification activities against the applicable procurement document requirement
or, in the case of generic qualification, against the applicable QA criteria.
An overall assessment of identified deficiencies (1) suggests that some vendor
qualification activities may not adequately support the applicable NRC require- ments, and (2) emphasizes the need for increased licensee attention to the adequacy
of their vendor procurement control practices for qualification activities and
the definition of responsibilities and interfaces in the qualification process.
Documentation from vendors and test laboratories form the basis for meeting the
equipment qualification requirements of paragraphs (d), (e), (f) and (j) of 10 CFR 50.49. This documentation may include procurement specifications, test plans, test procedures, test logbooks, qualification test reports, test data, analyses
and corrective action to resolve test anomalies, test configurations and
interfaces, and quality assurance information.
The NRC staff considers the above-identified deficiencies to be representative
examples of problems with vendors and test laboratories providing qualification
services to other vendors and user utilities. Although there may be specific
problems applicable to a particular utility, the staff expects that user
utilities will consider the overall applicability of the above information in
establishing qualification of safety-related equipment.
No specific action or written response is required by this notice. If you have
any questions regarding this notice, please contact the Regional Administrator
of the appropriate NRC regional office or this office.
ar l. orian, Director
Divis n of Emergency Preparedness
and ngineering Response
Office of Inspection and Enforcement
Technical Contact:
G. T. Hubbard, IE
(301) 492-9759 Attachment: List of Recently Issued IE Information Notices
Attachment 1 IN 85-40
May 22, 1985 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
85-39 Auditability of Electrical 5/22/85 All power reactor
Equipment Qualification facilities holding
Records At Licensees' an OL or CP
Facilities
85-38 Loose Parts Obstruct Control 5/21/85 All PWR facilities
Rod Drive Mechanism designed by B&W
85-37 Chemical Cleaning Of Steam 5/14/85 All pressure water
Generator At Milestone 2 reactor facilities
84-55 Seal Table Leaks At PWRs 5/14/85 All power reactor
Sup. 1 facilities holding
85-20 Motor-Operated Valve Failures 5/14/85 All power reactor
Sup. 1 Due To Hammering Effect facilities holding
85-36 Malfunction Of A Dry-Storage, 5/9/85 All licensees
Panoramic, Gamma Exposure possessing gamma
Irradiator irradiators
84-52 Inadequate Material 5/8/85 All power reactor
Sup. 1 Procurement Controls On facilities holding
The Part Of Licensees And an OL or CP
Vendors
85-35 Failure Of Air Check Valves 4/30/85 All power reactor
To Seat facilities holding
85-34 Heat Tracing Contributes To 4/30/85 All power reactor
Corrosion Failure Of Stainless facilities holding
84-84 Deficiencies In Ferro- 4/24/85 All power reactor
Rev. 1 Resonant Transformers facilities holding
DL = Operating License
CP = Construction Permit