ML20083G903

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Revised Non-Cited Violation - Monticello Nuclear Generating Plant NRC Component Design Bases Inspection Report 05000263/2015007
ML20083G903
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 03/20/2020
From: O'Brien K
NRC/RGN-III
To: Church C
Northern States Power Company, Minnesota
References
EA-15-206
Download: ML20083G903 (8)


See also: IR 05000263/2015007

Text

March 20, 2020

EA-15-206

Mr. Christopher Church

Site Vice President

Monticello Nuclear Generating Plant

Northern States Power Company, Minnesota

2807 West County Road 75

Monticello, MN 55362-9637

SUBJECT: REVISED NON-CITED VIOLATIONMONTICELLO NUCLEAR

GENERATING PLANT NRC COMPONENT DESIGN BASES INSPECTION

REPORT 05000263/2015007 (NCV 05000263/2015007-02; FAILURE TO

REVIEW FOR SUITABILITY OF APPLICATION OF SAFETY-RELATED

RELAYS INSTALLED BEYOND THEIR SERVICE LIFE)

Dear Mr. Church:

On October 2, 2015, Monticello Nuclear Generating Plant (MNGP) provided a written

response to U.S. Nuclear Regulatory Commission (NRC) Inspection Report 05000263/2015007,

which was issued on September 2, 2015. Specifically, the letter contested Non-Cited Violation 05000263/2015007-02 associated with the failure to justify continued service of safety-related

relays and motor starter contactors installed beyond their service life. The letter explained

MNGP agreed a performance deficiency occurred but disagreed the deficiency was associated

with a violation of Title 10 of the Code of Federal Regulations (CFR), Part 50, Appendix B,

Criterion III, Design Control, as stated in the inspection report. The letter further stated MNGP

believed the performance deficiency was associated with 10 CFR Part 50, Appendix B,

Criterion V, Instructions, Procedures, and Drawings.

The NRC carefully reviewed MNGPs reply and determined the Non-Cited Violation should

be changed to a violation of Technical Specifications 5.4.1, Procedures, as shown in the

enclosed assessment. Technical Specification 5.4.1, requires, in part, the establishment,

implementation, and maintenance of written procedures recommended in Regulatory

Guide 1.33, Revision 2, Appendix A, February 1978. Section 9 of the Regulatory Guide

requires the development of preventive maintenance schedules and associated procedures

for the inspection or replacement of parts that have a specific lifetime. The bases for the

staffs conclusion are detailed in the enclosed report.

C. Church

-2-

This letter, its enclosure, MNGPs October 2, 2015, response, and your response (if any) will be

made available for public inspection and copying at http://www.nrc.gov/reading- rm/adams.html

and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections,

Exemptions, Requests for Withholding.

Sincerely,

/RA/

Kenneth G. OBrien, Director

Division of Reactor Safety

Docket No. 50-263

License No. DPR-22

Enclosure:

NRC Staff Assessment of Disputed

NCV 05000263/2015007-02

cc: Distribution via LISTSERV

C. Church

-3-

Letter to Christopher Church from Kenneth G. OBrien dated March 20, 2020.

SUBJECT: REVISED NON-CITED VIOLATIONMONTICELLO NUCLEAR

GENERATING PLANT NRC COMPONENT DESIGN BASES INSPECTION

REPORT 05000263/2015007 (NCV 05000263/2015007-02; FAILURE TO

REVIEW FOR SUITABILITY OF APPLICATION OF SAFETY-RELATED

RELAYS INSTALLED BEYOND THEIR SERVICE LIFE)

DISTRIBUTION:

Jessie Quichocho

Omar Lopez-Santiago

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Darrell Roberts

John Giessner

Jamnes Cameron

Allan Barker

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ADAMS Accession Number: ML20083G903

OFFICE

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NAME

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JCameron

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JPeralta

DATE

02/25/20

02/25/20

03/18/20 via Email

02/26/20 via Email

OFFICE

RIII

NAME

KOBrien

DATE

03/20/20 via Email

OFFICIAL RECORD COPY

NRC STAFF ASSESSMENT OF DISPUTED NCV 05000263/2015007-02

Enclosure

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed information provided in

the Monticello Nuclear Generating Plant (MNGP) letter dated October 2, 2015. This review

was performed by staff members having relevant technical and regulatory knowledge.

Documents referenced are listed in the Reference Section of this Enclosure.

1. BACKGROUND

During the 2012 Problem Identification and Resolution inspection, Unresolved

Item (URI)05000263/2012008-01 was opened related to the qualification basis for

safety-related relays and motor starter contactors. The URI identified concerns regarding

the acceptability of keeping specific safety-related relays and motor starter contactors

installed in the plant for a period which exceeded the vendor recommended service life

without an appropriate justification.

The inspectors, in consultation with Nuclear Reactor Regulation staff, issued Task Interface

Agreement (TIA) 2014-01, Final Task Interface Agreement - Regulatory Position on Design

Life of Safety-Related Structures, Systems, and Components Related to Unresolved Items

at Donald C. Cook Nuclear Power Plant, Monticello Nuclear Generating Plant and Palisades

Nuclear Plant, on May 7, 2015. This TIA concluded when a licensee becomes aware that

a safety-related structure, system or components (SSCs) service life has been exceeded or

information challenges the presumption that a safety-related SSC can perform its specified

function, the licensee must promptly address and document this non-conforming condition in

accordance with the licensees NRC approved Quality Assurance Program, the licensees

operability/functionality program and the corrective action program. This includes

completing appropriate corrective actions in a timely manner and documenting evaluations

justifying the service life extensions.

On September 2, 2015, the NRC issued Component Design Bases Inspection

Report 05000263/2015007 that assessed, in part, the unresolved item discussed above.

The NRC documented the closure of the URI as a finding of very-low safety significance

(Green) and an associated Non-Cited Violation (NCV) of Title 10 of the Code of Federal

Regulations (CFR), Part 50, Appendix B, Criterion III, for the failure to review for suitability

of application of safety-related relays and motor starter contactors, which were installed

beyond their service life. This inspection report dispositioned this issue as NCV 05000263/2015007-02. Immediate corrective actions included instituting a Relay Monitoring

Program, performing generic service life evaluations on specific types of safety-related

relays, and identifying and replacing relays that had exceeded the vendor recommended

service life. The licensee continued to identify safety-related relays exceeding the vendor

recommended service life and had plans to conduct extent of condition reviews. A separate

corrective action item was initiated to evaluate motor starter contactors installed beyond the

recommended service life.

On October 2, 2015, MNGP provided a written response to the NRC contesting the

enforcement decision associated with NCV 05000263/2015007-02. Specifically, the letter

explained MNGP agreed a performance deficiency occurred but disagreed it was associated

with a violation of 10 CFR Part 50, Appendix B, Criterion III, as stated in the inspection

report. Rather, MNGP stated the performance deficiency was associated with a violation of

10 CFR Part 50, Appendix B, Criterion V.

NRC STAFF ASSESSMENT OF DISPUTED NCV 05000263/2015007-02

2

2. ORIGINAL ENFORCEMENT DECISION

The original enforcement decision as stated in Inspection Report 05000263/2015007 was:

Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part, that

measures shall be established for the selection and review for suitability of application of

materials, parts, equipment, and processes that are essential to the safety-related functions

of structures, systems, and components.

Contrary to the above, as of July 24, 2015, the licensee failed to establish measures to

ensure the selection and review for suitability of application of materials, parts, equipment,

and processes that were essential to the safety-related functions of structures, systems or

components. Specifically, the licensee did not review for suitability of application of

safety-related Agastat and General Electric relays and motor starter contactors that

exceeded their service life, a condition nonconforming to their design basis, to justify their

continued service considering in-service deterioration.

3. LICENSEE POSITION

In a letter dated October 2, 2015, the licensee stated MNGP agreed a performance

deficiency occurred but disagreed it was associated with a violation of 10 CFR Part 50,

Appendix B, Criterion III, as stated in the inspection report. The letter further stated MNGP

believed the performance deficiency was associated with 10 CFR Part 50, Appendix B,

Criterion V. The basis for the licensees position was, in part, that regulatory requirements

(including Criterion V) required the establishment of maintenance schedules as opposed to

strictly adhering to vendor recommendations or formally evaluating deviations from those

recommendations under a quality assurance program established to meet 10 CFR Part 50,

Appendix B. The licensee agreed it had not established a preventive maintenance schedule

for replacing specific Agastat and General Electric relays or motor starter contactors. In

addition, the licensee asserted that issuance of NCV 05000263/2015007-02 was premature

because the underlying NRC staff position may be changed due to the ongoing

development of a Regulatory Issue Summary (RIS) by the NRC.

4. NRC STAFF REVIEW

The NRC staff considered MNGPs assertion that regulatory requirements and NRC

endorsed quality assurance program standards do not require licensees to strictly adhere

to vendor recommendations or formally evaluate deviations from those recommendations

under the Appendix B quality assurance program. The NRC staff agreed that a licensee

may not have requirements involving strict adherence to vendor recommendations, unless

specified in other design and licensing basis documents. However, the NRC staff

determined that current regulations required licensees to establish quality assurance

programs and supporting procedures that, among other things, set preventive maintenance

schedules for the inspection or replacement of parts that have a specific lifetime.

In this case, the licensees preventive maintenance template used for scheduling preventive

maintenance activities established a specific lifetime for safety-related relays and contactors

classified as critical components. However, no preventive maintenance schedule or

associated procedures were developed for safety-related relays and motor starter

contactors classified as non-critical components.

NRC STAFF ASSESSMENT OF DISPUTED NCV 05000263/2015007-02

3

As discussed in the licensees letter, the failure to develop procedures to ensure continued

quality of the safety-related relays and motor starter contactors during the equipment

operational phase could be dispositioned as a violation of 10 CFR Part 50, Appendix B,

Criterion V, which requires, in part, activities affecting quality to be prescribed by

documented procedures of a type appropriate to the circumstances. Similarly, the issue

could be dispositioned as a violation of Technical Specification Section 5.4.1, Procedures,

which requires, in part, the establishment, implementation, and maintenance of written

procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February

1978. Section 9 of the Regulatory Guide requires the development of preventive

maintenance schedules and associated procedures for the inspection or replacement

of parts that have a specific lifetime.

Finally, the staff considered the licensees position that any inspection finding in this matter

should await the development of a RIS. Since the licensees letter, the NRC decided to not

issue a RIS as explained in the Statements of Considerations published by the NRC in

83 FR 46199 (September 12, 2018). Instead of issuing a RIS, the NRC provided training to

inspectors in 2018 to, in part, assist them in identifying and dispositioning issues related to

how long safety-related structures, systems, and components remain in service and clarify

the applicability of various regulations and industry standards.

5. CONCLUSION

The NRC staff carefully considered the information provided by MNGP in its letter

dated October 2, 2015, and determined the original enforcement decision of

NCV 05000263/2015007-02 should be modified as follows:

Technical Specification 5.4.1, Procedures, states, in part, that written procedures shall

be established, implemented, and maintained covering the applicable procedures

recommended in Regulatory Guide 1.33, Quality Assurance Program Requirements,

Revision 2, Appendix A, February 1978. Regulatory Guide 1.33, Revision 2, Appendix A,

Section 9, Procedures for Performing Maintenance, requires, in part, that preventive

maintenance schedules shall be developed for the inspection or replacement of parts that

have a specific lifetime.

Contrary to the above, as of July 24, 2015, the licensee failed to establish, implement

and maintain applicable procedures recommended in Section 9 of Regulatory Guide 1.33,

Revision 2, Appendix A, February 1978. Specifically, the licensee did not develop a

preventive maintenance schedule for inspecting or replacing various safety-related relays

and motor starter contactors classified as non-critical, which had a specific lifetime.

6. REFERENCES

1. Letter from Mohammed A. Shuaibi to Aby S. Mohseni; Final Task Interface

AgreementRegulatory Position on Design Life of Safety-Related Structures, Systems,

and Components Related to Unresolved Items at Donald C. Cook Nuclear Power Plant,

Monticello Nuclear Generating Plant, and Palisades Nuclear Plant (TIA 2014-01);

May 7, 2015.

NRC STAFF ASSESSMENT OF DISPUTED NCV 05000263/2015007-02

4

2. Letter from Christine A. Lipa to Mr. Peter A. Gardner; Monticello Nuclear Generating

Plant NRC Component Design Bases Inspection Report 05000263/2015007;

September 2, 2015.

3. Letter from Peter A. Gardner to the NRC Document Control Desk; Response to

Non-Cited Violation Dated September 2, 2015; October 2, 2015.

4. Letter from Edwin M. Hackett to Victor M. McCree; Committee to Review Generic

Requirements: Minutes of Meeting Numbers 446 and 447; October 17, 2017.

5. Definitions; 10 CFR 50.2; 2015-2017.

6. Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants;

10 CFR Part 50, Appendix B; 2015-2017.

7. Requirements for monitoring the effectiveness of maintenance at nuclear power plants;

10 CFR 50.65; 2015-2017.

8. Regulatory Guide 1.33; February 1978; Quality Assurance Program Requirements;

U.S. Nuclear Regulatory Commission; Washington, DC.

9. Regulatory Guide 1.186; December 2000; Guidance and Examples for Identifying

10 CFR 50.2 Design Bases; U.S. Nuclear Regulatory Commission; Washington, DC.

10. 34 FR 6599; Quality Assurance Criteria for Nuclear Power Plants; Federal Register;

Volume 34; p. 6599; Washington, DC; April 17, 1969.

11. 35 FR 10498; Quality Assurance Criteria for Nuclear Power Plants; Federal Register;

Volume 35; p. 10498; Washington, DC; June 27, 1970.

12. 48 FR 2729; Environmental Qualification of Electric Equipment Important to Safety

for Nuclear Power Plants; Federal Register; Volume 48; p. 2729; Washington, DC;

January 21, 1983.

13. 60 FR 22478; Nuclear Power Plant License Renewal; Federal Register; Volume 60;

p. 22478; Washington, DC; May 8, 1995.

14. 81 FR 30571; Disposition of Information Related to the Time Period That Safety-

Related Structures, Systems, or Components Are Installed; Federal Register;

Volume 81; p. 30571; Washington, DC; May 17, 2016.

15. 83 FR 46199; Disposition of Information Related to the Time Period That Safety-

Related Structures, Systems, or Components Are Installed; Federal Register;

Volume 83; p. 46199; Washington, DC; September 12, 2018.

16. NRC Enforcement Manual; Revisions 9 and 10.

17. NRC Enforcement Policy; February 4, 2015, and November 1, 2016.

18. Revised Appendix B to NEI 97-04; Guidance and Examples for Identifying 10 CFR 50.2

Design Bases; November 2000.

NRC STAFF ASSESSMENT OF DISPUTED NCV 05000263/2015007-02

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19. Inspector Guidance (Training) on Service Life Issues; June 2018; ML18219A470.

20. SL-009555; Preventive Maintenance Optimization for Agastat Relays using Refine

Maintenance Optimization, Revision 0.

21. SL-009558; Preventive Maintenance Optimization for G.E. Relays using Refine

Maintenance Optimization, Revision 0.

22. Issue ID 500001446684; MNGP Relay Program Issues; September 15, 2014.

23. Work Order 700029534-0010; One-Time Relay Replacement-23A-K9; June 13, 2018.