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| {{#Wiki_filter:SSINS No.: 6835 IN 85-40 UNITED STATES NUCLEAR REGULATORY | | {{#Wiki_filter:SSINS No.: 6835 IN 85-40 |
|
| |
|
| COMMISSION | | ===UNITED STATES=== |
| | NUCLEAR REGULATORY COMMISSION |
|
| |
|
| OFFICE OF INSPECTION | | ===OFFICE OF INSPECTION AND ENFORCEMENT=== |
| | WASHINGTON, D.C. |
|
| |
|
| ===AND ENFORCEMENT===
| | 20555 |
| WASHINGTON, D.C. 20555 May 22, 1985 IE INFORMATION
| |
|
| |
|
| NOTICE NO. 85-40: DEFICIENCIES | | ===May 22, 1985=== |
| | IE INFORMATION NOTICE NO. 85-40: |
|
| |
|
| IN EQUIPMENT
| | ===DEFICIENCIES IN EQUIPMENT QUALIFICATION=== |
| | | TESTING AND CERTIFICATION PROCESS |
| ===QUALIFICATION=== | |
| TESTING AND CERTIFICATION | |
| | |
| PROCESS | |
|
| |
|
| ==Addressees== | | ==Addressees== |
| : | | : |
| All holders of a nuclear power reactor operating | | All holders of a nuclear power reactor operating license (OL) or a construction |
| | |
| license (OL) or a construction | |
|
| |
|
| permit (CP). | | permit (CP). |
|
| |
|
| ==Purpose== | | ==Purpose== |
| : This information | | : |
| | | This information notice is to alert licensees that quality-related deficiencies |
| 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
| | in the qualification documentation, review, approval, and certification process |
|
| |
|
| supporting
| | have been identified by the Vendor Program Branch (VPB) of the NRC during its |
|
| |
|
| environmental
| | review of qualification activities. |
|
| |
|
| qualification | | ===NRC observations suggest that some vendor=== |
| | qualification activities and practices may not provide a sufficient basis for |
|
| |
|
| of safety-related
| | qualification certification. |
|
| |
|
| equipment
| | It is suggested that recipients review this information for specific and generic |
|
| |
|
| at their facilities
| | applicability to ensure that documentation supporting environmental qualification |
|
| |
|
| is complete. | | of safety-related equipment at their facilities is complete. |
|
| |
|
| Suggestions | | Suggestions |
|
| |
|
| contained | | contained in this notice do not constitute NRC requirements; therefore, no |
|
| |
|
| in this notice do not constitute
| | specific action or response is required. |
|
| |
|
| NRC requirements;
| | ==Description of Circumstances== |
| therefore, no specific action or response is required.Description
| | : |
| | 10 CFR 50.49, Regulatory Guide 1.89 (Revision 1, June 1984), and IEEE Standards |
|
| |
|
| of Circumstances:
| | 323-1974 and 323-1983 each require auditable information demonstrating qualifi- cation to provide continuing assurance to licensee management and the NRC that |
| 10 CFR 50.49, Regulatory
| |
|
| |
|
| Guide 1.89 (Revision
| | equipment in use is qualified for the entire period during which it is installed |
|
| |
|
| 1, June 1984), and IEEE Standards 323-1974 and 323-1983 each require auditable
| | in the nuclear power plant. |
|
| |
|
| information
| | 10 CFR 50, Appendix B, provides quality assurance |
|
| |
|
| demonstrating
| | requirements for the generation of all elements of qualification files. |
|
| |
|
| qualifi-cation to provide continuing
| | IEEE |
|
| |
|
| assurance
| | Standard 323-1974, Section 8 (endorsed by Regulatory Guide 1.89), requires that |
|
| |
|
| to licensee management
| | individual elements of qualification files be reviewed and approved by the |
|
| |
|
| and the NRC that equipment
| | licensee. Since July 1982, the VPB has actively inspected vendor qualification |
|
| |
|
| in use is qualified
| | efforts for compliance to these NRC requirements. |
|
| |
|
| for the entire period during which it is installed in the nuclear power plant. 10 CFR 50, Appendix B, provides quality assurance requirements
| | ===Inspections have been performed=== |
| | at manufacturing facilities, independent testing laboratories, architect-engineers, and nuclear steam supply system (NSSS) vendors. |
|
| |
|
| for the generation
| | NRC observations at the vendor level provide examples where more active licensee |
|
| |
|
| of all elements of qualification
| | participation in the qualification effort should have occurred. |
|
| |
|
| files. IEEE Standard 323-1974, Section 8 (endorsed
| | In some cases, certification of qualification is now difficult to justify because of documen- tation and test practices employed by vendors. |
|
| |
|
| by Regulatory
| | ===Some examples of NRC findings=== |
| | follow. |
|
| |
|
| Guide 1.89), requires that individual
| | 8505200600 |
|
| |
|
| elements of qualification
| | IN 85-40 |
| | May 22, 1985 1. Qualification activities not performed under a QA program consistent with |
|
| |
|
| files be reviewed and approved by the licensee.
| | 10 C 5, Appenx |
|
| |
|
| Since July 1982, the VPB has actively inspected
| | I |
|
| |
|
| vendor qualification
| | o |
|
| |
|
| efforts for compliance
| | Qualification testing of Class lE equipment was conducted without |
|
| |
|
| to these NRC requirements.
| | appropriate QA programs. |
|
| |
|
| Inspections
| | o |
|
| |
|
| have been performed at manufacturing
| | No QA requirements were imposed on organizations providing safety- related services (such as irradiation, calibration, and analyses) |
| | associated with the qualification process. |
|
| |
|
| facilities, independent
| | 2. Qualification test report conclusions not supported by test data or |
|
| |
|
| testing laboratories, architect-engineers, and nuclear steam supply system (NSSS) vendors.NRC observations
| | test data not availab e |
|
| |
|
| at the vendor level provide examples where more active licensee participation
| | o |
|
| |
|
| in the qualification | | Test profiles shown in qualification reports were not actually achieved |
|
| |
|
| effort should have occurred.
| | during test. |
|
| |
|
| In some cases, certification
| | o |
|
| |
|
| of qualification
| | Reports identified specimens or materials that were different from |
|
| |
|
| is now difficult
| | those actually tested. |
|
| |
|
| to justify because of documen-tation and test practices
| | o |
|
| |
|
| employed by vendors. Some examples of NRC findings follow.8505200600
| | Test records showed inadequate sensitivity/resolution of test equipment. |
| IN 85-40 May 22, 1985 1. Qualification
| |
|
| |
|
| activities
| | o |
|
| |
|
| not performed
| | Documentation required by the standards referenced in the test report |
|
| |
|
| under a QA program consistent
| | was not available (test plans, equipment lists, and calibration records). |
|
| |
|
| with 10 C 5, Appenx I o Qualification
| | ° |
| | Test anomalies werenot adequately reported or evaluated. |
|
| |
|
| testing of Class lE equipment
| | o |
|
| |
|
| was conducted | | Similarity between test specimens and items to be qualified was not |
|
| |
|
| without appropriate
| | established. |
|
| |
|
| QA programs.o No QA requirements
| | 3. Documentation to support the validity of |
|
| |
|
| were imposed on organizations
| | qualification not maintained |
|
| |
|
| providing
| | for lifetime of the equipment |
|
| |
|
| safety-related services (such as irradiation, calibration, and analyses)associated
| | o |
|
| |
|
| with the qualification
| | Supporting test data were destroyed after five years. |
|
| |
|
| process.2. Qualification
| | 4. Inadequate review, approval, or certification of test results |
|
| |
|
| test report conclusions
| | o |
|
| |
|
| not supported
| | Interfaces/responsibilities of organizations involved in the |
|
| |
|
| by test data or test data not availab e o Test profiles shown in qualification
| | qualification process were not clearly defined. |
|
| |
|
| reports were not actually achieved during test.o Reports identified
| | o |
|
| |
|
| specimens
| | Test reports contained statements that testing satisfied the |
|
| |
|
| or materials | | "guidelines" or "intent" of standards referenced in the specification. |
|
| |
|
| that were different
| | Detailed descriptions of NRC findings and results of these inspections are |
|
| |
|
| from those actually tested.o Test records showed inadequate
| | published in NUREG-0040, "Licensee Contractor and Vendor Inspection Status |
|
| |
|
| sensitivity/resolution
| | 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 |
|
| |
|
| of test equipment.
| | Printing Office, Post Office Box 37082, Washington, D.C. |
|
| |
|
| o Documentation
| | 20013-7982. |
|
| |
|
| required by the standards
| | IN 85-40 |
| | May 22, 1985 Correspondence with contractors and vendors relative to the inspection data |
|
| |
|
| referenced
| | contained in NUREG-0040 is placed in the NRC Public Document Room, 1717 H Street, N. W., Washington, D.C. |
|
| |
|
| in the test report was not available (test plans, equipment
| | 20555. |
|
| |
|
| lists, and calibration
| | Discussion: |
| | The deficiencies described in this notice resulted from the review of a vendor's |
|
| |
|
| records).° Test anomalies
| | qualification activities against the applicable procurement document requirement |
|
| |
|
| werenot adequately
| | or, in the case of generic qualification, against the applicable QA criteria. |
|
| |
|
| reported or evaluated.
| | An overall assessment of identified deficiencies (1) suggests that some vendor |
|
| |
|
| o Similarity
| | qualification activities may not adequately support the applicable NRC require- ments, and (2) emphasizes the need for increased licensee attention to the adequacy |
|
| |
|
| between test specimens
| | of their vendor procurement control practices for qualification activities and |
|
| |
|
| and items to be qualified | | the definition of responsibilities and interfaces in the qualification process. |
|
| |
|
| was not established.
| | Documentation from vendors and test laboratories form the basis for meeting the |
|
| |
|
| 3. Documentation
| | equipment qualification requirements of paragraphs (d), (e), (f) and (j) of 10 |
| | CFR 50.49. |
|
| |
|
| to support the validity of qualification
| | This documentation may include procurement specifications, test plans, test procedures, test logbooks, qualification test reports, test data, analyses |
|
| |
|
| not maintained
| | and corrective action to resolve test anomalies, test configurations and |
|
| |
|
| for lifetime of the equipment o Supporting
| | interfaces, and quality assurance information. |
|
| |
|
| test data were destroyed
| | The NRC staff considers the above-identified deficiencies to be representative |
|
| |
|
| after five years.4. Inadequate
| | examples of problems with vendors and test laboratories providing qualification |
|
| |
|
| review, approval, or certification
| | services to other vendors and user utilities. Although there may be specific |
|
| |
|
| of test results o Interfaces/responsibilities
| | problems applicable to a particular utility, the staff expects that user |
|
| |
|
| of organizations | | utilities will consider the overall applicability of the above information in |
|
| |
|
| involved in the qualification
| | establishing qualification of safety-related equipment. |
|
| |
|
| process were not clearly defined.o Test reports contained
| | No specific action or written response is required by this notice. |
|
| |
|
| statements
| | If you have |
|
| |
|
| that testing satisfied
| | any questions regarding this notice, please contact the Regional Administrator |
|
| |
|
| the"guidelines" or "intent" of standards | | of the appropriate NRC regional office or this office. |
|
| |
|
| referenced
| | ar l. orian, Director |
|
| |
|
| in the specification.
| | ===Divis n of Emergency Preparedness=== |
| | and ngineering Response |
|
| |
|
| Detailed descriptions
| | ===Office of Inspection and Enforcement=== |
|
| |
|
| of NRC findings and results of these inspections
| | ===Technical Contact:=== |
|
| |
|
| are published
| | ===G. T. Hubbard, IE=== |
| | (301) 492-9759 Attachment: |
|
| |
|
| in NUREG-0040, "Licensee
| | ===List of Recently Issued IE Information Notices=== |
|
| |
|
| Contractor
| | ===Attachment 1=== |
| | IN 85-40 |
|
| |
|
| and Vendor Inspection
| | ===May 22, 1985=== |
| | LIST OF RECENTLY ISSUED |
|
| |
|
| Status Report," Volumes 6, 7, and 8. This report is published
| | ===IE INFORMATION NOTICES=== |
| | Information |
|
| |
|
| quarterly
| | Date of |
|
| |
|
| by the NRC, and it can be obtained from the Superintendent
| | Notice No. |
|
| |
|
| of Documents, U.S. Government
| | Subject |
|
| |
|
| Printing Office, Post Office Box 37082, Washington, D.C. 20013-7982.
| | Issue |
|
| |
|
| IN 85-40 May 22, 1985 Correspondence
| | Issued to |
|
| |
|
| with contractors
| | 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 |
|
| |
|
| and vendors relative to the inspection
| | 5/22/85 |
|
| |
|
| data contained
| | ===Equipment Qualification=== |
| | | Records At Licensees' |
| in NUREG-0040
| | Facilities |
| 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
| | Loose Parts Obstruct Control 5/21/85 |
|
| |
|
| regarding
| | ===Rod Drive Mechanism=== |
| | Chemical Cleaning Of Steam |
|
| |
|
| this notice, please contact the Regional Administrator
| | 5/14/85 |
|
| |
|
| of the appropriate
| | ===Generator At Milestone 2=== |
| | Seal Table Leaks At PWRs |
|
| |
|
| NRC regional office or this office.ar l. orian, Director Divis n of Emergency
| | 5/14/85 Motor-Operated Valve Failures 5/14/85 |
|
| |
|
| ===Preparedness=== | | ===Due To Hammering Effect=== |
| and ngineering
| | Malfunction Of A Dry-Storage, 5/9/85 |
|
| |
|
| Response Office of Inspection
| | ===Panoramic, Gamma Exposure=== |
| | Irradiator |
|
| |
|
| and Enforcement
| | Inadequate Material |
|
| |
|
| Technical
| | 5/8/85 |
|
| |
|
| Contact: G. T. Hubbard, IE (301) 492-9759 Attachment:
| | ===Procurement Controls On=== |
| List of Recently Issued IE Information
| | The Part Of Licensees And |
|
| |
|
| Notices
| | Vendors |
|
| |
|
| Attachment
| | Failure Of Air Check Valves |
|
| |
|
| 1 IN 85-40 May 22, 1985 LIST OF RECENTLY ISSUED IE INFORMATION
| | 4/30/85 To Seat |
| | |
| 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
| | Heat Tracing Contributes To |
|
| |
|
| At Milestone
| | 4/30/85 |
|
| |
|
| 2 Seal Table Leaks At PWRs 5/14/85 Motor-Operated
| | ===Corrosion Failure Of Stainless=== |
| | Steel Piping |
|
| |
|
| Valve Failures 5/14/85 Due To Hammering
| | Deficiencies In Ferro- |
| | 4/24/85 |
|
| |
|
| Effect Malfunction
| | ===Resonant Transformers=== |
| | All power reactor |
|
| |
|
| Of A Dry-Storage, 5/9/85 Panoramic, Gamma Exposure Irradiator
| | facilities holding |
|
| |
|
| Inadequate
| | an OL or CP |
|
| |
|
| Material 5/8/85 Procurement
| | ===All PWR facilities=== |
| | designed by B&W |
|
| |
|
| Controls On The Part Of Licensees
| | holding an OL or CP |
|
| |
|
| And Vendors Failure Of Air Check Valves 4/30/85 To Seat Heat Tracing Contributes
| | ===All pressure water=== |
| | reactor facilities |
|
| |
|
| To 4/30/85 Corrosion
| | holding an OL or CP |
|
| |
|
| Failure Of Stainless Steel Piping Deficiencies
| | ===All power reactor=== |
| | facilities holding |
|
| |
|
| In Ferro- 4/24/85 Resonant Transformers
| | an OL or CP |
|
| |
|
| All power reactor facilities | | ===All power reactor=== |
| | facilities holding |
|
| |
|
| holding an OL or CP All PWR facilities
| | an OL or CP |
|
| |
|
| designed by B&W holding an OL or CP All pressure water reactor facilities
| | ===All licensees=== |
| | possessing gamma |
|
| |
|
| holding an OL or CP All power reactor facilities
| | irradiators |
|
| |
|
| holding an OL or CP All power reactor facilities
| | ===All power reactor=== |
| | facilities holding |
|
| |
|
| holding an OL or CP All licensees possessing
| | an OL or CP |
|
| |
|
| gamma irradiators
| | ===All power reactor=== |
| | facilities holding |
|
| |
|
| All power reactor facilities
| | an OL or CP |
|
| |
|
| holding an OL or CP All power reactor facilities
| | ===All power reactor=== |
| | facilities holding |
|
| |
|
| holding an OL or CP All power reactor facilities
| | an OL or CP |
|
| |
|
| holding an OL or CP All power reactor facilities
| | ===All power reactor=== |
| | 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}} |
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) |
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Category:NRC Information Notice
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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
|
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| list | - Information Notice 1985-01, Continuous Supervision of Irradiators (10 January 1985)
- Information Notice 1985-02, Improper Installation and Testing of Differential Pressure Transmitters (11 January 1985)
- Information Notice 1985-03, Separation of Primary Reactor Coolant Pump Shaft and Impeller (15 January 1985)
- Information Notice 1985-04, Inadequate Management of Security Response Drills (17 January 1985)
- Information Notice 1985-05, Pipe Whip Restraints (23 January 1985)
- Information Notice 1985-06, Contamination of Breathing Air Systems (23 January 1985, Topic: Spent fuel rack)
- Information Notice 1985-07, Contaminated Radiography Source Shipments (29 January 1985)
- Information Notice 1985-08, Industry Experience on Certain Materials Used in Safety-Related Equipment (30 January 1985)
- Information Notice 1985-09, Isolation Transfer Switches and Post-Fire Shutdown Capability (31 January 1985, Topic: Safe Shutdown)
- Information Notice 1985-10, Posttensioned Containment Tendon Anchor Head Failure (6 February 1985, Topic: Stress corrosion cracking)
- Information Notice 1985-11, Licensee Programs for Inspection of Electrical Raceway and Cable Installations (11 February 1985)
- Information Notice 1985-12, Recent Fuel Handling Events (11 February 1985, Topic: Eddy Current Testing)
- Information Notice 1985-13, Consequences of Using Soluble Dams (21 February 1985, Topic: Hydrostatic)
- Information Notice 1985-14, Failure of a Heavy Control Rod (B4C) Drive Assembly to Insert on a Trip Signal (22 February 1985)
- Information Notice 1985-15, Nonconforming Structural Steel for Safety-Related Use (22 February 1985)
- Information Notice 1985-16, Time/Current Trip Curve Discrepancy of ITE/Siemens-Allis Molded Case Circuit Breaker (27 February 1985)
- Information Notice 1985-17, Possible Sticking of Asco Solenoid Valves (1 March 1985)
- Information Notice 1985-18, Failures of Undervoltage Output Circuit Boards in the Westinghouse-Designed Sold State Protection System (7 March 1985)
- Information Notice 1985-19, Alleged Falsification of Certifications and Alteration of Markings on Piping, Valves, and Fittings (11 March 1985)
- Information Notice 1985-20, Motor-Operated Valve Failures Due to Hampering Effect (12 March 1985)
- Information Notice 1985-21, Main Steam Isolation Valve Closure Logic (18 March 1985)
- Information Notice 1985-22, Failure of Limitorque Motor-Operated Valves Resulting from Incorrect Installation of Pinion Gear (21 March 1985)
- Information Notice 1985-23, Inadequate Surveillance and Postmaintenance and Postmodification System Testing (22 March 1985)
- Information Notice 1985-24, Failures of Protective Coatings in Pipes and Heat Exchangers (26 March 1985, Topic: Ultimate heat sink, Coatings)
- Information Notice 1985-25, Consideration of Thermal Conditions in the Design and Installation of Supports for Diesel Generator Exhaust Silencers (2 April 1985, Topic: Coatings)
- Information Notice 1985-26, Vacuum Relief System for Boiling Water Reactor Mark I and Mark II Containments (2 April 1985, Topic: Coatings)
- Information Notice 1985-27, Notifications to the NRC Operations Center and Reporting Events in Licensee Event Reports (3 April 1985, Topic: Coatings)
- Information Notice 1985-28, Partial Loss of AC Power and Diesel Generator Degradation (9 April 1985, Topic: Coatings, Overspeed)
- Information Notice 1985-30, Microbiologically Induced Corrosion of Containment Service Water System (19 April 1985, Topic: Hydrostatic, Coatings, Biofouling)
- Information Notice 1985-31, Buildup of Enriched Uranium in Ventilation Ducts and Associated Effluent Treatment Systems (19 April 1985, Topic: Coatings)
- Information Notice 1985-32, Recent Engine Failures of Emergency Diesel Generators (22 April 1985, Topic: Coatings)
- Information Notice 1985-33, Undersized Nozzle-To-Shell Welded Joints in Tanks and Heat Exchangers Constructed Under the Rules of the ASME Boiler and Pressure Vessel Code (22 April 1985)
- Information Notice 1985-34, Heat Tracing Contributes to Corrosion Failure of Stainless Steel Piping (30 April 1985, Topic: Hydrostatic)
- Information Notice 1985-35, Failure of Air Check Valves to Seat (30 April 1985, Topic: Loss of Offsite Power)
- Information Notice 1985-35, Failure of Air Check Valves To Seat (30 April 1985, Topic: Loss of Offsite Power)
- Information Notice 1985-37, Chemical Cleaning of Steam Generators at Millstone 2 (14 May 1985, Topic: Feedwater Heater, Eddy Current Testing)
- Information Notice 1985-38, Loose Parts Obstruct Control Rod Drive Mechanism (21 May 1985)
- Information Notice 1985-39, Auditability of Electrical Equipment Qualification Records at Licensees Facilities (22 May 1985)
- Information Notice 1985-40, Deficiencies in Equipment Qualification Testing and Certification Process (22 May 1985)
- Information Notice 1985-43, Radiography Events at Power Reactors (30 May 1985, Topic: High Radiation Area, Scaffolding)
- Information Notice 1985-44, Emergency Communication System Monthly Test (30 May 1985, Topic: Health Physics Network)
- Information Notice 1985-46, Clarification of Several Aspects of Removable Radioactive Surface Contamination Limits for Transport Packages (10 June 1985)
- Information Notice 1985-47, Potential Effect of Line-Induced Vibration on Certain Target Rock Solenoid-Operated Valves (18 June 1985)
- Information Notice 1985-48, Respirator Users Notice: Defective Self Contained Breathing Apparatus Air Cylinders (19 June 1985, Topic: Hydrostatic)
- Information Notice 1985-49, Relay Calibration Problem (1 July 1985)
- Information Notice 1985-50, Complete Loss of Main and Auxiliary Feedwater at a PWR Designed by Babcock & Wilcox (8 July 1985, Topic: Overspeed trip, Overspeed)
- Information Notice 1985-51, Inadvertent Loss or Improper Actuation of Safety-Related Equipment (10 July 1985)
- Information Notice 1985-52, Errors in Dose Assessment Computer Codes and Reporting Requirements Under 10 CFR Part 21 (10 July 1985, Topic: Basic Component)
- Information Notice 1985-53, Performance of NRC-Licensed Individuals While on Duty (12 July 1985)
- Information Notice 1985-54, Teletherapy Unit Malfunction (15 July 1985)
... further results |
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