Information Notice 1998-42, Implementation of 10 CFR 55.55a(g) Inservice Inspection Requirements

Implementation of 10 CFR 55.55a(g) Inservice Inspection Requirements

ML031040543
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, Three Mile Island, 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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant
Issue date:	12/01/1998
From:	Roe J Office of Nuclear Reactor Regulation
To:
References
IN-98-042, NUDOCS 9811240114
Download: ML031040543 (8)

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UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 December 1, 1998 NRC INFORMATION NOTICE 98-42: IMPLEMENTATION OF 10 CFR 50.55a(g) INSERVICE

INSPECTION REQUIREMENTS

Addressees

All holders of operating licenses for nuclear power reactors.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) Is Issuing this Information notice to alert

addressees to certain aspects of requesting relief from American Society of Mechanical

Engineers Boiler and Pressure Vessel Code (ASME Code) examinations that received less than

essentially 100 percent" coverage. ("Essentially 100 percent" examination is defined as more

than 90 percent of the specified examination volume.) It Is expected that recipients will review

the information for applicability to their facilities and consider actions, as appropriate, to avoid

similar problems. However, suggestions contained inthis Information notice are not NRC

requirements; therefore, no specific action or written response is required.

Description of Circumstances

It became evident to the NRC staff while it was conducting Inservice inspections (ISI) reviews of

licensees' 90-day ISI reports that some licensees were unaware of, uncertain of, or had

misinterpreted the Title 10 of the Code of Federal Regulations 50.55a(g)(4) (10 CFR

50.55a(g)(4)) requirements regarding the examination of components to the extent practical

within the limitations of design, geometry, and materials of construction of the components.

Licensees should be cognizant of 10 CFR 50.55a(g)(5)(iii) which requires submittal of requests

for relief from paragraph 50.55a(g)(4) when complete examination coverage(s) Is impractical.

Because of the scope and extent of ISI examinations, significant planning Is necessary to

address the technical and regulatory Issues associated with the examinations required by the

ASME Code, to the extent practical, of Class 1, 2, and 3 systems and components.

This information notice contains a discussion of certain areas of misinterpretation that the NRC

staff has dealt with In the Implementation of the 10 CFR 50.55a(g)(4) rule.

98 ) A2li/ ADD In K 58 -oo' 1 14m

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 December 1, 1998 NRC INFORMATION NOTICE 98-42: IMPLEMENTATION OF 10 CFR 50.55a(g) INSERVICE

INSPECTION REQUIREMENTS

Addressees

All holders of operating licenses for nuclear power reactors.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) Is Issuing this Information notice to alert

addressees to certain aspects of requesting relief from American Society of Mechanical

Engineers Boiler and Pressure Vessel Code (ASME Code) examinations that received less than

essentially 100 percent" coverage. ("Essentially 100 percent" examination Is defined as more

than 90 percent of the specified examination volume.) It Is expected that recipients will review

the information for applicability to their facilities and consider actions, as appropriate, to avoid

similar problems. However, suggestions contained in this Information notice are not NRC

requirements; therefore, no specific action or written response Is required.

Description of Circumstances

It became evident to the NRC staff while it was conducting inservice Inspections (ISI) reviews of

licensees' 90-day ISI reports that some licensees were unaware of, uncertain of, or had

misinterpreted the Title 10 of the Code of Federal Regulations 50.55a(g)(4) (10 CFR

50.55a(g)(4)) requirements regarding the examination of components to the extent practical

within the limitations of design, geometry, and materials of construction of the components.

Licensees should be cognizant of 10 CFR 50.55a(g)(5)(iii) which requires submittal of requests

for relief from paragraph 50.55a(g)(4) when complete examination coverage(s) Is impractical.

Because of the scope and extent of ISI examinations, significant planning is necessary to

address the technical and regulatory Issues associated with the examinations required by the

ASME Code, to the extent practical, of Class 1, 2, and 3 systems and components.

This information notice contains a discussion of certain areas of misinterpretation that the NRC

staff has dealt with In the Implementation of the 10 CFR 50.55a(g)(4) rule.

• .) ~ IN 98-42 December 1, 1998 Discussion

In 10 CFR 50.55a(g)(5)(iil), It is requested that requests for relief from limited

submitted when it Is Impractical to complete the examination coverage requirements examinations be

Xl of the ASME Code. Recent NRC reviews found that several licensees did of Section

requests for relief from examinations of less than essentially 100 percent coverage.not submit

licensees correctly interpreted 10 CFR 50.55a(g)(4) for Class 1,2, and 3 componentsThe

that they were required to perform the ASME Code examinations to the extent to mean

However, the licensees misinterpreted the requirement to mean that they were practical.

submit requests for relief from examinations that received less than essentially not required to

coverage because they had examined the component to the extent practical. 100 percent

At least one licensee quoted 10 CFR 50.55a(g)(4) as a basis for not seeking

to obtain the required examination coverage. In 10 CFR 50.55a(g)(4) it Isstated, relief when unable

in part, that

components... must meet the requirements... to the extent practical within

design, geometry and materials of construction of the components." However, the limitations of

incomplete or partial ISI examination coverage required by the ASME Code when

Is obtained, NRC

relief Is required pursuant to 10 CFR 50.55a(g)(5)(iii).

During discussions with the NRC staff regarding Its review of a 90-day

was determined that a licensee had obtained "essentially 100 percent" ISI summary report, It

coverage for most

examinations but had obtained coverage of 90 percent or less on several components.

Contrary to the requirements of the rule, the licensee did not submit requests

NRC on the basis of Impracticality before 1 year after the end of the effective for relief to the

required by 10 CFR 50.55a(g)(5)(iv), unti the NRC pointed out this omission. Interval as

'Essentially100 Percent" Examination Standard

After many inquiries and interpretations, ASME Issued ASME Code Case N-460,

Examination Coverage for Class 1 and 2 Welds," Section Xi, Division 1,dated "Alternative

ASME Code Case N-460 states, Inpart, that "when the entire examination July 27, 1988.

volume

cannot be examined. . . a reduction Inexamination coverage ... may be accepted or area

reduction in coverage for that weld Is less than 10 percent. The NRC has adopted provided the

refined the definition of "essentially 100 percent" to mean 'greater than 90 and further

percent" in 10 CFR

50.55a(g)(6)(ii)(A)(2) for required examination coverage of reactor pressure

standard has been applied to all examinations of welds or other areas required vessel welds. This

Section Xi. by ASME

Most licensees are finding that although the overall average examination coverage

may be more than 90 percent, examination coverage for other Individual welds for all welds

substantially less than 90 percent. When a licensee Is unable to examine "essentiallybe may

percent" of each weld, It must seek relief frorn the NRC Inaccordance with 100

50.55a(g)(5)(iii). 10 CFR

• ActIN 98-42 December 1, 1998 This Information notice requires no specific action or written

reminded that they are required to consider Industry-wide response. However, recipients are

Information notices), where practical, when setting goals operating experience (including NRC

and performing periodic evaluations

under 10 CFR 50.65, Requirements for monitoring the

effectiveness

power plants." If you have any questions about the Information of maintenance at nuclear

the technical contact listed below or the appropriate Office In this notice, please contact

of Nuclear Reactor Regulation

(NRR) project manager.

Jt W. Roe, Acting Director

!on of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contact: Thomas K. McLellan, NRR

301- 415-2716 E-mail: tkm@nrc.gov

Attachment: List of Recently Issued NRC Information

Notices

/jhAi}g> jet

,-Attachment

IN 98-42 December 1, 1998 Page 1 of I

LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

98-41 Spurious Shutdown of Emergency 11/20/98 All holders of operating licenses

Diesel Generators from Design for nuclear power reactors, except

Oversight for those who have ceased

operations and have certified that

fuel has been permanently

removed from the reactor vessel

98-40 Design Deficiencies Can Lead 10/26/98 All holders of operating licenses

Reduced ECCS Pump Net Positive for nuclear power reactors, except

Suction Head During Design-Basis those licensees who have

Accidents permanently ceased operations

and have certified that fuel has

bee permanently removed from

the vessel

98-39 Summary of Fitness-for-Duty 10124/98 All holders of operating licenses

Program Performance Reports for for nuclear power reactors

Calendar Years 1996 and 1997

98-38 Metal-Clad Circuit Breaker 10/15/98 All holders of operating licenses

Maintenance Issued Identified for nuclear power reactors.

By NRC Inspections

98-37 Eligibility of Operator License 10/01/98 All holders of operating licenses

Applicants for nuclear power reactors, except those who have

permanently ceased operations

and have certified that fuel has

been permanently removed from

the reactor vessel.

98-36 Inadequate or Poorly Controlled 9/18198 All holders of operating licenses

Non-Safety-Related Maintenance for nuclear power reactors

Activities Unnecessarily Challenged

Safety Systems

OL = Operating License

CP = Construction Permit

IN 98-42 December 1, 1998 This information notice requires no specific action or written response. However, recipients are

reminded that they are required to consider industry-wide operating experience (including NRC

information notices), where practical, when setting goals and performing periodic evaluations

under 10 CFR 50.65, Requirements for monitoring the effectiveness of maintenance at nuclear

power plants." If you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation

(NRR) project manager

Original signed by

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contact: Thomas K. McLellan, NRR

301- 415-2716 E-mail: tkm@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

DOCUMENT NAME: S:\drpmsec\98-42.in

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OFFICE PECB:DRPM I TECH ED* I N ECGB:DE Il C:ECGB:DE D:DE l

NAME TGreene* BCalure* TMcLellan* GBagchi* GLainas*

DATE j 11/12198 10/30/98 11/12/98 111/13/98 I II

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NAME RDennig* JStolz* JRoe( LS '

DATE 11/23/98 11/24/98 11 215 /98 AcJ

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IN 98-XX

November XX, 1998 This information notice requires no specific action or written response. However, recipients are

reminded that they are required to consider industry-wide operating experience (including NRC

information notices), where practical, when setting goals and performing periodic evaluations

under 10 CFR 50.65, Requirements for monitoring the effectiveness of maintenance at nuclear

power plants." If you have any questions about the information in this notice, please contact

the technical contact listed below or the appropriate Office of Nuclear Reactor Regulation

(NRR) project manager

Jack W. Roe, Acting Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contact: Thomas K. McLellan, NRR

301- 415-2716 E-mail: tkm@nrc.gov

Attachment: List of Recently Issued NRC Information Notices

DOCUMENT NAME: G:\TAGINISI e kt

To receive a coDY of this document. indicate in the box C=Coov wlo attachmentlenclosure E=Copwwith ditachmentlenclosure N = No copy

OFFICE PECB:DRPMl TECH ED* IN ECGB:DE l C D:DE

NAME TGreene (9 BCalure TMcLellan* ) Bagchi GLainap

DATE on /_

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OFFICE PECB _,

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NAME RDennj _

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DATE {l / 1"-/98 1lI/IL[I98 I /98

- See previous concurrence

OFFICIAL RECORD COPY

- DOCUMENT NAME:

To receive a copy of this document, indicate in the box C=Copy wlo attachment/enclosure E=Copy with attachment/enclosure N = No copy

[OFFICE

NAME

DATE

PECB:DRPM I

T. Greene

I/ /98

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OFFICE SC/PECB:DRPM I BC/PECB:DRPM I DIDRPM l

NAME R. Dennig J. Stolz J ..Roe

DATE 1/ 98 I /98 I /98 OFFICIAL RECORD COPY

DOCUMENT NAME: G:\TAG\INISI

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