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 NUCLEAR REGULATORY
{{#Wiki_filter:SSINS No.: 6835 IN 85-40
                                  UNITED STATES


COMMISSION
NUCLEAR REGULATORY COMMISSION


OFFICE OF INSPECTION
OFFICE OF INSPECTION AND ENFORCEMENT


===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


NOTICE NO. 85-40: DEFICIENCIES
TESTING AND CERTIFICATION PROCESS
 
IN EQUIPMENT
 
===QUALIFICATION===
TESTING AND CERTIFICATION
 
PROCESS


==Addressees==
==Addressees==
:
:
All holders of a nuclear power reactor operating
                                                      license (OL) or a construction
 
license (OL) or a construction


===All holders of a nuclear power reactor operating===
permit (CP).
permit (CP).


==Purpose==
==Purpose==
: This information
:
                                                  that quality-related deficiencies


notice is to alert licensees
This information notice is to alert licenseesapproval, and certification process


that quality-related
in the qualification documentation, review, Branch (VPB) of the NRC during its


deficiencies
have been identified by the Vendor Programobservations suggest that some vendor


in the qualification
review of qualification activities. NRC      not provide a sufficient basis for


documentation, review, approval, and certification
qualification activities and practices may


process have been identified
qualification certification.


by the Vendor Program Branch (VPB) of the NRC during its review of qualification
information for specific and generic


activities.
It is suggested that recipients review this supporting environmental qualification


NRC observations
applicability to ensure that documentation          is complete. Suggestions


suggest that some vendor qualification
of safety-related equipment at their facilities


activities
NRC requirements; therefore, no


and practices
contained in this notice do not constitute


may not provide a sufficient
specific action or response is required.


basis for qualification
==Description of Circumstances==
 
:
certification.
                                                  1, June 1984), and IEEE Standards
 
It is suggested
 
that recipients
 
review this information


for specific and generic applicability
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 ensure that documentation
cation to provide continuing assurance to      period during which it is installed


supporting
equipment in use is qualified for the entire          B, provides quality assurance


environmental
in the nuclear power plant. 10 CFR 50, Appendix of qualification files. IEEE


qualification
requirements for the generation of all elements


of safety-related
Regulatory Guide 1.89), requires that


equipment
Standard 323-1974, Section 8 (endorsed by be reviewed and approved by the


at their facilities
individual elements of qualification files          inspected vendor qualification


is complete.
licensee. Since July 1982, the VPB has actively        Inspections have been performed


Suggestions
efforts for compliance to these NRC requirements.


contained
testing laboratories, architect-engineers, at manufacturing facilities, independent


in this notice do not constitute
and nuclear steam supply system (NSSS) vendors.


NRC requirements;
examples where more active licensee
therefore, no specific action or response is required.Description


of Circumstances:
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
10 CFR 50.49, Regulatory


Guide 1.89 (Revision
tation and test practices employed by vendors.


1, June 1984), and IEEE Standards 323-1974 and 323-1983 each require auditable
follow.


information
8505200600


demonstrating
IN 85-40
                                                                              May 22, 1985 1.    Qualification activities not performed under a QA


qualifi-cation to provide continuing
10 C 5, Appenx                                            program consistent with


assurance
I


to licensee management
o      Qualification testing of Class lE equipment


and the NRC that equipment
appropriate QA programs.                        was conducted without


in use is qualified
o      No QA requirements were imposed on organizations


for the entire period during which it is installed in the nuclear power plant. 10 CFR 50, Appendix B, provides quality assurance requirements
related services (such as irradiation,                providing safety- associated with the qualification process.calibration,     and analyses)
  2.    Qualification test report conclusions not


for the generation
test data not availab e                      supported by test data or


of all elements of qualification
o      Test profiles shown in qualification reports


files. IEEE Standard 323-1974, Section 8 (endorsed
during test.                                       were not actually achieved


by Regulatory
o      Reports identified specimens or materials


Guide 1.89), requires that individual
those actually tested.                         that were different from


elements of qualification
o     Test records showed inadequate sensitivity/resolution
 
files be reviewed and approved by the licensee.
 
Since July 1982, the VPB has actively inspected
 
vendor qualification
 
efforts for compliance
 
to these NRC requirements.
 
Inspections
 
have been performed at manufacturing
 
facilities, independent
 
testing laboratories, architect-engineers, and nuclear steam supply system (NSSS) vendors.NRC observations
 
at the vendor level provide examples where more active licensee participation
 
in the qualification
 
effort should have occurred.
 
In some cases, certification
 
of qualification
 
is now difficult
 
to justify because of documen-tation and test practices
 
employed by vendors. Some examples of NRC findings follow.8505200600
IN 85-40 May 22, 1985 1. Qualification
 
activities
 
not performed
 
under a QA program consistent
 
with 10 C 5, Appenx I o Qualification
 
testing of Class lE equipment
 
was conducted
 
without appropriate
 
QA programs.o No QA requirements
 
were imposed on organizations
 
providing
 
safety-related services (such as irradiation, calibration, and analyses)associated
 
with the qualification
 
process.2. Qualification
 
test report conclusions
 
not supported
 
by test data or test data not availab e o Test profiles shown in qualification
 
reports were not actually achieved during test.o Reports identified
 
specimens
 
or materials
 
that were different
 
from those actually tested.o Test records showed inadequate
 
sensitivity/resolution


of test equipment.
of test equipment.


o Documentation
o     Documentation required by the standards
 
required by the standards
 
referenced


in the test report was not available (test plans, equipment
was not available (test plans, equipment referenced in the test report


lists, and calibration
lists, and calibration records).


records).° Test anomalies
°     Test anomalies werenot adequately reported or evaluated.


werenot adequately
o      Similarity between test specimens and items


reported or evaluated.
established.                                     to be qualified was not


o Similarity
3.    Documentation to support the validity of


between test specimens
for lifetime oftheequipment                qualification not maintained


and items to be qualified
o      Supporting test data were destroyed after


was not established.
five years.


3. Documentation
4. Inadequate review, approval, or certification


to support the validity of qualification
of test results


not maintained
o      Interfaces/responsibilities of organizations


for lifetime of the equipment o Supporting
qualification process were not clearly            involved in the


test data were destroyed
defined.


after five years.4. Inadequate
o    Test reports contained statements that testing


review, approval, or certification
"guidelines" or "intent" of standards referencedsatisfied the
 
of test results o Interfaces/responsibilities
 
of organizations
 
involved in the qualification
 
process were not clearly defined.o Test reports contained
 
statements
 
that testing satisfied
 
the"guidelines" or "intent" of standards
 
referenced


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


of NRC findings and results of these inspections
Report," Volumes 6, 7, and 8. This report          and Vendor Inspection Status


are published
is


in NUREG-0040, "Licensee
and it can be obtained from the Superintendent published quarterly by the NRC,
Printing Office, Post Office Box 37082,            of Documents, U.S. Government


Contractor
Washington, D.C. 20013-7982.


and Vendor Inspection
IN 85-40
                                                                  May 22, 1985 Correspondence with contractors and vendors relative to the inspection data


Status Report," Volumes 6, 7, and 8. This report is published
contained in NUREG-0040 is placed in the NRC Public Document Room, 1717 H Street, N. W., Washington, D.C. 20555.


quarterly
Discussion:
The deficiencies described in this notice resulted from the review of a vendor's


by the NRC, and it can be obtained from the Superintendent
qualification activities against the applicable procurement document requirement


of Documents, U.S. Government
or, in the case of generic qualification, against the applicable QA criteria.


Printing Office, Post Office Box 37082, Washington, D.C. 20013-7982.
An overall assessment of identified deficiencies (1) suggests that some vendor


IN 85-40 May 22, 1985 Correspondence
qualification activities may not adequately support the applicable NRC require- ments, and (2) emphasizes the need for increased licensee attention to the adequacy


with contractors
of their vendor procurement control practices for qualification activities and


and vendors relative to the inspection
the definition of responsibilities and interfaces in the qualification process.


data contained
Documentation from vendors and test laboratories form the basis for meeting the


in NUREG-0040
equipment qualification requirements of paragraphs (d), (e), (f) and (j) of 10
is placed in the NRC Public Document Room, 1717 H Street, N. W., Washington, D.C. 20555.Discussion:
CFR 50.49. This documentation may include procurement specifications, test plans, test procedures, test logbooks, qualification test reports, test data, analyses
The deficiencies


described
and corrective action to resolve test anomalies, test configurations and


in this notice resulted from the review of a vendor's qualification
interfaces, and quality assurance information.


activities
The NRC staff considers the above-identified deficiencies to be representative


against the applicable
examples of problems with vendors and test laboratories providing qualification


procurement
services to other vendors and user utilities. Although there may be specific


document requirement
problems applicable to a particular utility, the staff expects that user


or, in the case of generic qualification, against the applicable
utilities will consider the overall applicability of the above information in


QA criteria.An overall assessment
establishing qualification of safety-related equipment.


of identified
No specific action or written response is required by this notice. If you have


deficiencies
any questions regarding this notice, please contact the Regional Administrator


(1) suggests that some vendor qualification
of the appropriate NRC regional office or this office.


activities
ar l. orian, Director


may not adequately
Divis n of Emergency Preparedness


support the applicable
and ngineering Response


NRC require-ments, and (2) emphasizes
Office of Inspection and Enforcement


the need for increased
===Technical Contact:===


licensee attention
===G. T. Hubbard, IE===
                      (301) 492-9759 Attachment:  List of Recently Issued IE Information Notices


to the adequacy of their vendor procurement
Attachment 1 IN 85-40
                                                                May 22, 1985 LIST OF RECENTLY ISSUED


control practices
IE INFORMATION NOTICES


for qualification
Information                                      Date of


activities
Notice No.      Subject                        Issue    Issued to


and the definition
85-39            Auditability of Electrical      5/22/85  All power reactor


of responsibilities
Equipment Qualification                  facilities holding


and interfaces
Records At Licensees'                    an OL or CP


in the qualification
Facilities
 
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
85-38            Loose Parts Obstruct Control    5/21/85  All PWR facilities


and Enforcement
Rod Drive Mechanism                      designed by B&W


Technical
holding an OL or CP
 
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 85-38 85-37 84-55 Sup. 1 85-20 Sup. 1 85-36 84-52 Sup. 1 85-35 85-34 84-84 Rev. 1 Auditability
 
of Electrical
 
5/22/85 Equipment
 
===Qualification===
Records At Licensees'
Facilities


Loose Parts Obstruct Control 5/21/85 Rod Drive Mechanism Chemical Cleaning Of Steam 5/14/85 Generator
85-37            Chemical Cleaning Of Steam     5/14/85   All pressure water


At Milestone
Generator At Milestone 2                  reactor facilities


2 Seal Table Leaks At PWRs 5/14/85 Motor-Operated
holding an OL or CP


Valve Failures 5/14/85 Due To Hammering
84-55            Seal Table Leaks At PWRs        5/14/85 All power reactor


Effect Malfunction
Sup. 1                                                    facilities holding


Of A Dry-Storage, 5/9/85 Panoramic, Gamma Exposure Irradiator
an OL or CP


Inadequate
85-20            Motor-Operated Valve Failures 5/14/85    All power reactor


Material 5/8/85 Procurement
Sup. 1          Due To Hammering Effect                  facilities holding


Controls On The Part Of Licensees
an OL or CP


And Vendors Failure Of Air Check Valves 4/30/85 To Seat Heat Tracing Contributes
85-36            Malfunction Of A Dry-Storage, 5/9/85     All licensees


To 4/30/85 Corrosion
Panoramic, Gamma Exposure                possessing gamma


Failure Of Stainless Steel Piping Deficiencies
Irradiator                                irradiators


In Ferro- 4/24/85 Resonant Transformers
84-52            Inadequate Material            5/8/85   All power reactor


All power reactor facilities
Sup. 1          Procurement Controls On                  facilities holding


holding an OL or CP All PWR facilities
The Part Of Licensees And                an OL or CP


designed by B&W holding an OL or CP All pressure water reactor facilities
Vendors


holding an OL or CP All power reactor facilities
85-35            Failure Of Air Check Valves    4/30/85  All power reactor


holding an OL or CP All power reactor facilities
To Seat                                    facilities holding


holding an OL or CP All licensees possessing
an OL or CP


gamma irradiators
85-34            Heat Tracing Contributes To    4/30/85  All power reactor


All power reactor facilities
Corrosion Failure Of Stainless            facilities holding


holding an OL or CP All power reactor facilities
Steel Piping                              an OL or CP


holding an OL or CP All power reactor facilities
84-84            Deficiencies In Ferro-          4/24/85  All power reactor


holding an OL or CP All power reactor facilities
Rev. 1          Resonant Transformers                    facilities holding


holding an OL or CP DL = Operating
an OL or CP


License CP = Construction
DL = Operating License


Permit}}
CP = Construction Permit}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Revision as of 02:37, 24 November 2019

Deficiencies in Equipment Qualification Testing and Certification Process
ML031180380
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, 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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane
Issue date: 05/22/1985
From: Jordan E
NRC/IE
To:
References
IN-85-040, NUDOCS 8505200600
Download: ML031180380 (4)


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

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

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.

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

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

holding an OL or CP

85-37 Chemical Cleaning Of Steam 5/14/85 All pressure water

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

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

Rev. 1 Resonant Transformers facilities holding

an OL or CP

DL = Operating License

CP = Construction Permit