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


===UNITED STATES===
NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION


OFFICE OF INSPECTION AND ENFORCEMENT
===OFFICE OF INSPECTION AND ENFORCEMENT===
WASHINGTON, D.C.


WASHINGTON, D.C. 20555 May 22, 1985 IE INFORMATION NOTICE NO. 85-40:    DEFICIENCIES IN EQUIPMENT QUALIFICATION
20555


===May 22, 1985===
IE INFORMATION NOTICE NO. 85-40:
===DEFICIENCIES IN EQUIPMENT QUALIFICATION===
TESTING AND CERTIFICATION PROCESS
TESTING AND CERTIFICATION PROCESS


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


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


==Purpose==
==Purpose==
:
:
                                                  that quality-related deficiencies
This information notice is to alert licensees that quality-related deficiencies


This information notice is to alert licenseesapproval, and certification process
in the qualification documentation, review, approval, and certification process


in the qualification documentation, review, Branch (VPB) of the NRC during its
have been identified by the Vendor Program Branch (VPB) of the NRC during its


have been identified by the Vendor Programobservations suggest that some vendor
review of qualification activities.


review of qualification activities. NRC      not provide a sufficient basis for
===NRC observations suggest that some vendor===
 
qualification activities and practices may not provide a sufficient basis for
qualification activities and practices may


qualification certification.
qualification certification.


information for specific and generic
It is suggested that recipients review this information for specific and generic


It is suggested that recipients review this supporting environmental qualification
applicability to ensure that documentation supporting environmental qualification


applicability to ensure that documentation          is complete. Suggestions
of safety-related equipment at their facilities is complete.


of safety-related equipment at their facilities
Suggestions


NRC requirements; therefore, no
contained in this notice do not constitute NRC requirements; therefore, no
 
contained in this notice do not constitute


specific action or response is required.
specific action or response is required.
Line 64: Line 65:
==Description of Circumstances==
==Description of Circumstances==
:
:
                                                  1, June 1984), and IEEE Standards
10 CFR 50.49, Regulatory Guide 1.89 (Revision 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 auditable information demonstrating qualifi- cation to provide continuing assurance to licensee management and the NRC that
  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 period during which it is installed


equipment in use is qualified for the entire          B, provides quality assurance
in the nuclear power plant.


in the nuclear power plant. 10 CFR 50, Appendix of qualification files. IEEE
10 CFR 50, Appendix B, provides quality assurance


requirements for the generation of all elements
requirements for the generation of all elements of qualification files.


Regulatory Guide 1.89), requires that
IEEE


Standard 323-1974, Section 8 (endorsed by be reviewed and approved by the
Standard 323-1974, Section 8 (endorsed by Regulatory Guide 1.89), requires that


individual elements of qualification files           inspected vendor qualification
individual elements of qualification files be reviewed and approved by the


licensee. Since July 1982, the VPB has actively       Inspections have been performed
licensee. Since July 1982, the VPB has actively inspected vendor qualification


efforts for compliance to these NRC requirements.
efforts for compliance to these NRC requirements.


testing laboratories, architect-engineers, at manufacturing facilities, independent
===Inspections have been performed===
at manufacturing facilities, independent testing laboratories, architect-engineers, and nuclear steam supply system (NSSS) vendors.


and nuclear steam supply system (NSSS) vendors.
NRC observations at the vendor level provide examples where more active licensee


examples where more active licensee
participation in the qualification effort should have occurred.


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
In some cases, certification of qualification is now difficult to justify because of documen- tation and test practices employed by vendors.
 
tation and test practices employed by vendors.


===Some examples of NRC findings===
follow.
follow.


Line 102: Line 102:


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


10 C 5, Appenx                                           program consistent with
10 C 5, Appenx


I
I


o     Qualification testing of Class lE equipment
o
 
Qualification testing of Class lE equipment was conducted without
 
appropriate QA programs.


appropriate QA programs.                        was conducted without
o


o      No QA requirements were imposed on organizations
No QA requirements were imposed on organizations providing safety- related services (such as irradiation, calibration, and analyses)
associated with the qualification process.


related services (such as irradiation,                providing safety- associated with the qualification process.calibration,    and analyses)
2. Qualification test report conclusions not supported by test data or
  2.   Qualification test report conclusions not


test data not availab e                       supported by test data or
test data not availab e


o     Test profiles shown in qualification reports
o


during test.                                      were not actually achieved
Test profiles shown in qualification reports were not actually achieved


o      Reports identified specimens or materials
during test.


those actually tested.                        that were different from
o


o    Test records showed inadequate sensitivity/resolution
Reports identified specimens or materials that were different from


of test equipment.
those actually tested.


o     Documentation required by the standards
o


was not available (test plans, equipment referenced in the test report
Test records showed inadequate sensitivity/resolution of test equipment.


lists, and calibration records).
o


°    Test anomalies werenot adequately reported or evaluated.
Documentation required by the standards referenced in the test report


o      Similarity between test specimens and items
was not available (test plans, equipment lists, and calibration records).


established.                                     to be qualified was not
°
Test anomalies werenot adequately reported or evaluated.


3.    Documentation to support the validity of
o


for lifetime oftheequipment                qualification not maintained
Similarity between test specimens and items to be qualified was not


o      Supporting test data were destroyed after
established.


five years.
3. Documentation to support the validity of


4. Inadequate review, approval, or certification
qualification not maintained


of test results
for lifetime of the equipment


o     Interfaces/responsibilities of organizations
o


qualification process were not clearly            involved in the
Supporting test data were destroyed after five years.


defined.
4. Inadequate review, approval, or certification of test results


o     Test reports contained statements that testing
o


"guidelines" or "intent" of standards referencedsatisfied the
Interfaces/responsibilities of organizations involved in the


in the specification.
qualification process were not clearly defined.


===Detailed descriptions of NRC findings and===
o
published in NUREG-0040, "Licensee Contractor  results of these inspections are


Report," Volumes 6, 7, and 8. This report          and Vendor Inspection Status
Test reports contained statements that testing satisfied the


is
"guidelines" or "intent" of standards referenced in the specification.


and it can be obtained from the Superintendent published quarterly by the NRC,
Detailed descriptions of NRC findings and results of these inspections are
Printing Office, Post Office Box 37082,            of Documents, U.S. Government


Washington, D.C. 20013-7982.
published in NUREG-0040, "Licensee Contractor and Vendor Inspection Status
 
Report," Volumes 6, 7, and 8. This report is published quarterly by the NRC,
and it can be obtained from the Superintendent of Documents, U.S. Government
 
Printing Office, Post Office Box 37082, Washington, D.C.
 
20013-7982.


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


contained in NUREG-0040 is placed in the NRC Public Document Room, 1717 H Street, N. W., Washington, D.C. 20555.
20555.


Discussion:
Discussion:
Line 202: Line 214:


equipment qualification requirements of paragraphs (d), (e), (f) and (j) of 10
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
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
and corrective action to resolve test anomalies, test configurations and
Line 220: Line 234:
establishing qualification of safety-related equipment.
establishing qualification of safety-related equipment.


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


any questions regarding this notice, please contact the Regional Administrator
any questions regarding this notice, please contact the Regional Administrator
Line 228: Line 244:
ar l. orian, Director
ar l. orian, Director


Divis n of Emergency Preparedness
===Divis n of Emergency Preparedness===
 
and ngineering Response
and ngineering Response


Office of Inspection and Enforcement
===Office of Inspection and Enforcement===


===Technical Contact:===
===Technical Contact:===


===G. T. Hubbard, IE===
===G. T. Hubbard, IE===
                      (301) 492-9759 Attachment:   List of Recently Issued IE Information Notices
(301) 492-9759 Attachment:  
 
===List of Recently Issued IE Information Notices===
 
===Attachment 1===
IN 85-40


Attachment 1 IN 85-40
===May 22, 1985===
                                                                May 22, 1985 LIST OF RECENTLY ISSUED
LIST OF RECENTLY ISSUED


IE INFORMATION NOTICES
===IE INFORMATION NOTICES===
Information


Information                                      Date of
Date of


Notice No.       Subject                        Issue    Issued to
Notice No.


85-39            Auditability of Electrical      5/22/85  All power reactor
Subject


Equipment Qualification                  facilities holding
Issue


Records At Licensees'                    an OL or CP
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
Facilities


85-38            Loose Parts Obstruct Control   5/21/85   All PWR facilities
Loose Parts Obstruct Control 5/21/85


Rod Drive Mechanism                       designed by B&W
===Rod Drive Mechanism===
Chemical Cleaning Of Steam


holding an OL or CP
5/14/85
 
===Generator At Milestone 2===
Seal Table Leaks At PWRs
 
5/14/85 Motor-Operated Valve Failures 5/14/85
 
===Due To Hammering Effect===
Malfunction Of A Dry-Storage, 5/9/85
 
===Panoramic, Gamma Exposure===
Irradiator
 
Inadequate Material
 
5/8/85
 
===Procurement Controls On===
The Part Of Licensees And
 
Vendors


85-37            Chemical Cleaning Of Steam      5/14/85  All pressure water
Failure Of Air Check Valves


Generator At Milestone 2                  reactor facilities
4/30/85 To Seat


holding an OL or CP
Heat Tracing Contributes To


84-55            Seal Table Leaks At PWRs        5/14/85 All power reactor
4/30/85


Sup. 1                                                    facilities holding
===Corrosion Failure Of Stainless===
Steel Piping


an OL or CP
Deficiencies In Ferro-
4/24/85


85-20            Motor-Operated Valve Failures 5/14/85    All power reactor
===Resonant Transformers===
All power reactor


Sup. 1          Due To Hammering Effect                  facilities holding
facilities holding


an OL or CP
an OL or CP


85-36            Malfunction Of A Dry-Storage, 5/9/85      All licensees
===All PWR facilities===
designed by B&W


Panoramic, Gamma Exposure                possessing gamma
holding an OL or CP


Irradiator                                irradiators
===All pressure water===
reactor facilities


84-52            Inadequate Material            5/8/85    All power reactor
holding an OL or CP


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


The Part Of Licensees And                an OL or CP
an OL or CP


Vendors
===All power reactor===
facilities holding
 
an OL or CP
 
===All licensees===
possessing gamma


85-35            Failure Of Air Check Valves    4/30/85  All power reactor
irradiators


To Seat                                    facilities holding
===All power reactor===
facilities holding


an OL or CP
an OL or CP


85-34            Heat Tracing Contributes To    4/30/85  All power reactor
===All power reactor===
facilities holding


Corrosion Failure Of Stainless            facilities holding
an OL or CP


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


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


Rev. 1          Resonant Transformers                    facilities holding
===All power reactor===
facilities holding


an OL or CP
an OL or CP

Latest revision as of 10:24, 16 January 2025

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

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

permit (CP).

Purpose

This information notice is to alert licensees that quality-related deficiencies

in the qualification documentation, review, approval, and certification process

have been identified by the Vendor Program Branch (VPB) of the NRC during its

review of qualification activities.

NRC observations suggest that some vendor

qualification activities and practices may not provide a sufficient basis for

qualification certification.

It is suggested that recipients review this information for specific and generic

applicability to ensure that documentation supporting environmental qualification

of safety-related equipment at their facilities is complete.

Suggestions

contained in this notice do not constitute NRC requirements; therefore, no

specific action or response is required.

Description of Circumstances

10 CFR 50.49, Regulatory Guide 1.89 (Revision 1, June 1984), and IEEE Standards

323-1974 and 323-1983 each require auditable information demonstrating qualifi- cation to provide continuing assurance to licensee management and the NRC that

equipment in use is qualified for the entire period during which it is installed

in the nuclear power plant.

10 CFR 50, Appendix B, provides quality assurance

requirements for the generation of all elements of qualification files.

IEEE

Standard 323-1974, Section 8 (endorsed by Regulatory Guide 1.89), requires that

individual elements of qualification 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.

o

Documentation required by the standards referenced in the test report

was not available (test plans, equipment lists, and calibration records).

°

Test anomalies werenot adequately reported or evaluated.

o

Similarity between test specimens and items to be qualified was not

established.

3. Documentation to support the validity of

qualification not maintained

for lifetime of the equipment

o

Supporting test data were destroyed after five years.

4. Inadequate review, approval, or certification 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.

Detailed descriptions of NRC findings and results of these inspections are

published in NUREG-0040, "Licensee Contractor and Vendor Inspection Status

Report," Volumes 6, 7, and 8. This report is published quarterly by the NRC,

and it can be obtained from the Superintendent of Documents, U.S. Government

Printing Office, Post Office Box 37082, 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

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 At Milestone 2

Seal Table Leaks At PWRs

5/14/85 Motor-Operated Valve Failures 5/14/85

Due To Hammering Effect

Malfunction Of A Dry-Storage, 5/9/85

Panoramic, Gamma Exposure

Irradiator

Inadequate Material

5/8/85

Procurement Controls On

The Part Of Licensees And

Vendors

Failure Of Air Check Valves

4/30/85 To Seat

Heat Tracing Contributes To

4/30/85

Corrosion Failure Of Stainless

Steel Piping

Deficiencies In Ferro-

4/24/85

Resonant Transformers

All power reactor

facilities holding

an OL or CP

All PWR facilities

designed by B&W

holding an OL or CP

All pressure water

reactor facilities

holding an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All licensees

possessing gamma

irradiators

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

DL = Operating License

CP = Construction Permit