Information Notice 1998-44, Ten-Year Inservice Inspection (ISI) Program Update for Licensees That Intend to Implement Risk-Informed ISI of Piping

Ten-Year Inservice Inspection (ISI) Program Update for Licensees That Intend to Implement Risk-Informed ISI of Piping

ML031040537
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane
Issue date:	12/10/1998
From:	Roe J Office of Nuclear Reactor Regulation
To:
References
IN-98-044, NUDOCS 9812100046
Download: ML031040537 (8)

UNITED STATES NUCLEAR REGULATORY

COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 December 10, 1998 NRC INFORMATION

NOTICE 98-44: TEN-YEAR INSERVICE

INSPECTION (ISI) PROGRAM UPDATE FOR LICENSEES

THAT INTEND TO IMPLEMENT

RISK-INFORMED

ISI OF PIPING

Addressees

All holders of operating

licenses for nuclear power reactors, except those that have permanently

ceased operations

and have certified

that fuel has been permanently

removed from the reactor.

Purpose

The U.S. Nuclear Regulatory

Commission (NRC) is issuing this information

notice to inform addressees

that for those licensees

that intend to implement

a risk-informed

inservice inspection (RI-ISI) program for piping and do not have a pilot plant application

currently

being reviewed by the staff, the staff will consider authorizing

a delay of up to 2 years in implementing

the next 1 0-year ISI program for piping only in order for the licensee to develop and obtain approval for the RI-ISI program for piping.It is expected that recipients

will review this information

for applicability

to their facilities

and consider actions, as appropriate.

However, suggestions

contained

in this information

notice are not NRC requirements;

therefore, no specific action or written response is required.Description

of Circumstances

On August 16, 1995, the NRC published

a policy statement

(60 FR 42622) on the use of probabilistic

risk assessment (PRA) methods in nuclear regulatory

activities.

In the statement, the Commission

stated its belief that the use of PRA technology

in NRC regulatory

activities

should be increased

to the extent supported

by the state of the art in PRA methods and data and in a manner that complements

the NRC's deterministic

approach.

To implement

this policy, the staff developed

a PRA implementation

plan, together with a timetable

for developing

regulatory

guides (RGs) and standard review plans (SRPs), which describes

an acceptable

approach for assessing

the nature and impact of changes by considering

engineering

issues and applying risk insights.

A part of this effort involves developing

an RG and the corresponding

SRP to provide guidance to power reactor licensees

and the NRC staff on an table approach for utilizing

risk information

to support requests for changes in the plant's 9812100046

4 'o q(OO qwOlo 9A

98-44 December 10, 1998 ISI program for piping. The draft documents

were available

for public comment through January 13, 1998, and the staff revised the draft documents

to incorporate

public comments.The RG and the SRP were issued for trial use on October 13, 1998.The nuclear industry has submitted

two topical reports describing

methodologies

for implementing

RI-ISI. One methodology

has been jointly developed

by the American Society of Mechanical

Engineers (ASME) and the Westinghouse

Owners Group (WOG). The other methodology

is being sponsored

by the Electric Power Research Institute (EPRI).In addition, ASME is working on three ASME Code cases for alternate

examination

requirements

to ASME Section Xl, Division 1, for piping welds. ASME Code Case N-577 is based on the WOG methodology

and ASME Code Case N-578 is based on the EPRI methodology.

ASME Code Case N-560 is based on the EPRI methodology

for Class 1 B-J welds and is being revised to encompass

both methodologies.

The NRC has encouraged

licensees

to submit pilot plant applications

for demonstrating

risk-informed methodologies

to be used for piping segment and piping structural

element selection in systems scheduled

for ISI. The NRC has completed

its review of the pilot plant submittal

for Vermont Yankee and is currently

reviewing

the submittals

for Surry Unit 1 and Arkansas Nuclear One, Units I and 2, focusing on the licensees'

characterization

of the proposed changes, including

identification

of the particular

piping systems and welds that are affected by the changes, the performance

of engineering

evaluations, the performance

of PRAs to provide risk insight to support the selection

of welds for inspection, the performance

of traditional

engineering

analyses to verify that the proposed changes do not compromise

the existing regulations

and the licensing

basis of the plant, the development

of implementation

and monitoring

programs to ensure that the reliability

of piping can be maintained, and the documentation

of the analyses for NRC's review and approval.

The staff will use the alternative

provision

of 10 CFR 50.55a (a)(3)(1)

to approve technically

acceptable

pilot plant applications.

Discussion

For non-pilot

plant licensees

that intend to implement

RI-ISI beginning

with their next 10-year interval, the staff will consider authorizing

a delay of up to 2 years in the implementation

of the next 1 0-year ISI program for piping only to allow licensees

to develop and obtain approval for their RI-ISI program at the next available

opportunity

using the staff-approved

topical reports.For those licensees

that are authorized

such a delay, the approved RI-ISI program would have to be completed

within the remaining

part of the 10-year interval, for example, programs would be shortened

to 8 years for a 2-year delay. The duration of the delay needed may vary according

to individual

cases. Therefore, the request for delay must provide adequate justification, along with a clear indication

of the inspection

that will continue before the implementation

of the RI-ISI program. During the delay period, licensees

would be required to continue augmented

inspection

programs, such as inspections

for intergranular

stress-corrosion

cracking and erosion-corrosion, inspections

required for flaws dispositioned

by analysis, system pressure tests, and inspection

of components

other than piping.

',_98-44 December 10, 1998 The staff plans to perform in-depth reviews of pilot plant submittals

during 1998 and 1999 to ensure that the RI-ISI programs are consistent

with the staff RG and SRP. For RI-ISI programs submitted

after the approval of the pilot plant programs and topical reports, but before the endorsement

of ASME Code cases, it Is expected that licensees

will utilize the approved WOG or EPRI topical report as guidance for developing

RI-ISI programs.

The review and approval process is expected to be minimal when the submittal

follows the guidelines

in the approved topical report, NRC Regulatory

Guide 1.178, wAn Approach for Plant-Specific

Risk-informed

Decisionmaking

Inservice

Inspection

of Piping"; Standard Review Plan 3.9.8, Standard Review Plan for the Review of Risk-Informed

Inservice

Inspection

of Piping"; and the safety evaluation

reports for the applicable

topical report.It is anticipated

that subsequent

to the issuance of safety evaluation

reports (SERs) for the pilot plants and the topical reports, the ASME Code cases will be revised to incorporate

lessons learned from pilot plants and topical report reviews. The ASME Code cases will be reviewed in accordance

with RG 1.147, Oinservice

Inspection

Code Case Acceptability

-ASME Section Xi, Division 1," for possible incorporation

into the ASME Code. In the long term, the staff will proceed with rulemaking

so that other licensees

can voluntarily

adopt risk-informed

ISI programs without specific review and approval by NRC. For the RI-ISI programs developed after the an RI-ISI methodology

has been endorsed in RG 1.147, the staff anticipates

that the licensee will develop an RI-ISI program using the approved ASME Code cases and will submit the program to NRC for information

with no formal NRC approval.If you have any questions

about the information

in this notice, please contact one of the technical

contacts listed below or the appropriate

NRR project manager.( d/Jack W. Roe, Acting Director Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical

Contacts:

S. Ali, NRR W. Burton, NRR 301-415-2776

301-415-2853 E-mail: saa3@nrc.gov

E-mail: wfb@nrc.gov

Attachment:

List of Recently Issued NRC Information

Notices 4aF4S 4 JA4OT,

\, Attachment

IN 98-44 December 10, 1998 LIST OF RECENTLY ISSUED NRC INFORMATION

NOTICES Information

Date of Notice No. Subject Issuance Issued to 98-43 Leaks in the Emergency

Diesel Generator

Lubricating

Oil and Jacket Cooling Water Piping 12/04/98 All holder of operating

licenses for nuclear power reactors, except those licensees

that have permanently

ceased operations

and have certified

that fuel has been permanently

removed from the reactor vessel 98-42 Implementation

of 10 CFR 50.55a 12/01/98 (g) Inservice

Inspection

Requirements

Spurious Shutdown of Emergency

11/20/98 Diesel Generators

from Design Oversight 98-41 98-40 Design Deficiencies

Can Lead Reduced ECCS Pump Net Positive Suction Head During Design-Basis

Accidents Summary of Fitness-for-Duty

Program Performance

Reports for Calendar Years 1996 and 1997 Metal-Clad

Circuit Breaker Maintenance

Issued Identified

By NRC Inspections

10/26/98 10/24/98 10/15/98 All holders of operating

licenses for nuclear power reactors All holders of operating

licenses for nuclear power reactors, except for those who have ceased operations

and have certified

that fuel has been permanently

removed from the reactor vessel All holders of operating

licenses for nuclear power reactors, except those licensees

who have permanently

ceased operations

and have certified

that fuel has bee permanently

removed from the vessel All holders of operating

licenses for nuclear power reactors All holders of operating

licenses for nuclear power reactors.98-39 98-38 OL = Operating

License CP = Construction

Permit

`n4 98-44 December 10, 1998 The staff plans to perform in-depth reviews of pilot plant submittals

during 1998 and 1999 to ensure that the RI-ISI programs are consistent

with the staff RG and SRP. For RI-ISI programs submitted

after the approval of the pilot plant programs and topical reports, but before the endorsement

of ASME Code cases, it is expected that licensees

will utilize the approved WOG or EPRI topical report as guidance for developing

RI-ISI programs.

The review and approval process is expected to be minimal when the submittal

follows the guidelines

in the approved topical report, NRC Regulatory

Guide 1.178, "An Approach for Plant-Specific

Risk-informed

Decisionmaking

Inservice

Inspection

of Piping"; Standard Review Plan 3.9.8, "Standard

Review Plan for the Review of Risk-Informed

Inservice

Inspection

of Piping"; and the safety evaluation

reports for the applicable

topical report.It is anticipated

that subsequent

to the issuance of safety evaluation

reports (SERs) for the pilot plants and the topical reports, the ASME Code cases will be revised to incorporate

lessons learned from pilot plants and topical report reviews. The ASME Code cases will be reviewed in accordance

with RG 1.147, "Inservice

Inspection

Code case Acceptability

-ASME Section Xl, Division 11," for possible incorporation

into the ASME Code. In the long term, the staff will proceed with rulemaking

so that other licensees

can voluntarily

adopt risk-informed

ISI programs without specific review and approval by NRC. For the RI-ISI programs developed after the RI-ISI methodology

has been endorsed in RG 1.147, the staff anticipates

that the licensee will develop an RI-ISI program using the approved ASME Code cases and will submit the program to NRC for information

with no formal NRC approval.If you have any questions

about the information

in this notice, please contact one of the technical

contacts listed below or the appropriate

NRR project manager.[original

signed by D.B. Matthews]f or Jack W. Roe, Acting Director Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical

Contacts:

S. Ali, NRR W. Burton, NRR 301-415-2776

301-415-2853 E-mail: saa3@nrc.gov

E-mail: wfb~nrc.gov

Attachment:

List of Recently Issued NRC Information

Notices DOCUMENT NAME: G:\ALI\INISI.WPD

• See Previous Concurrence

To receive a copy of this document, indicate in the box C=Copy w/o attachment/enclosure

E=Copy with attachment/enclosure

N-1 Nl lopy OFFICE PECB I (A)D:DE I C:ECG I [ l C:PECB (A NAME WBurton* .SAIi* GLainas* GBagchi* JMoore* JStolz* J VJ DATE j 9/17/98 9/17/98 j 9/29/98 9/17/98 11/26/98 12/04/98 1XI /198 OFFICIAL RECORD COPY

T'N 98-xx December xx, 1998 The staff plans to perform in-depth reviews of pilot plant submittals

during 1998 and 1999 to ensure that the RI-ISI programs are consistent

with the staff RG and SRP. For RI-ISI programs submitted

after the approval of the pilot plant programs and topical reports, but before the endorsement

of ASME Code cases, it is expected that licensees

will utilize the approved WOG or EPRI topical report as guidance for developing

RI-ISI programs.

The review and aX val process is expected to be minimal when the submittal

follows the guidelines

in th pproved topical report, NRC Regulatory

Guide 1.178, "An Approach for Plant-Specificgsk-lnformed

Decisionmaking

Inservice

Inspection

of Piping"; Standard Review Plan 3.., "Standard

Review Plan for the Review of Risk-informed

Inservice

Inspection

of Piping"; d the safety evaluation

reports for the applicable

topical report.It is anticipated

that subsequent

to the issuance of safety eva tion reports (SERs) for the pilot plants and the topical reports, the ASME Code cases will bI revised to incorporate

lessons learned from pilot plants and topical report reviews. The SME Code cases will be reviewed in accordance

with RG 1.147, "Inservice

Inspection

Cod case Acceptability

-ASME Section Xl, Division 1," for possible incorporation

into the ASM Code. In the long term, the staff will proceed with rulemaking

so that other licensees

voluntarily

adopt risk-informed

ISI programs without specific review and approval NRC. For the RI-ISI programs developed after the RI-ISI methodology

has been endord in RG 1.147, the staff anticipates

that the licensee will develop an RI-ISI program usi the approved ASME Code cases and will submit the program to NRC for information

with formal NRC approval.If you have any questions

about the i ormation in this notice, please contact one of the technical

contacts listed below or t appropriate

NRR project manager.Jack W. Roe, Acting Director Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical

Contacts:

S. Ali, NRR W. Burton, NRR 301-415-2776

301-415-2853 E-mail: saa3@nrc.gov

E-mail: wfb~nrc.gov

Attachment:

List of Recently Issued NRC Information

Notices DOCUMW T NAME: G:\ALI\IN

ISI.WPD* See P vious Concurrence

To receive a copy of this document, indicate in the box C=Copy wlo attachment/enclosure

E=Copy with attachmentlenclosure

N = No copy OFFICE PECB I E (A)D:DE lIC:ECGB LT C:PECB I (A)D:DRPM NAME WBurton* SAli* GLainas* GBagchi* JMoore* JfpI JRoe 11DATE 19/17198 19/17/98 19/29/98 19/17/98 111/26/98

/\ '/Ii~ / /98l OFFICIAL RECORD COPY V DATE /17/9 9/1798 9/9/98 /17/9 11/2/98 / 9 IN 98-xx October xx 1998 The staff plans to perform in-depth reviews of pilot plant submittals

during 1998 and 1999 to ensure that the RI-ISI programs are consistent

with the staff RG and SRP. For RI-ISI programs submitted

after the approval of the pilot plant programs and topical reports, but bWore the endorsement

of ASME Code Cases, it is expected that licensees

will utilize approved WOG or EPRI Topical Report as guidance for developing

RI-ISI programs.

TW review and approval process is expected to be minimal when the submittal

follows the gu lines in the approved Topical Report, NRC Regulatory

Guide 1.178, 'An Approach for P nt-Specific

Risk-Informed

Decision making Inservice

Inspection

of Piping", Standard Rev idw Plan 3.9.8, 'Standard

Review Plan for the Review of Risk-Informed

Inservice

Inspection

o 5iping", and the safety evaluation

reports for the applicable

topical report.It is anticipated

that subsequent

to the issuance of s ety evaluation

reports (SER) for the pilot plants and the topical reports, the industry will rev' e the ASME Code Cases to incorporate

lessons learned from pilot plants and topical re rt reviews. The ASME Code Cases will be endorsed by RG 1.147, "Inservice

Inspectio

ode Case Acceptability

-ASME Section Xl Division 1," and subsequently

incorporate

into the ASME Code. In the long term, the staff will proceed with rulemaking

so that other Ii nsees can voluntarily

adopt risk-informed

ISI programs without specific NRC review and app val. For the RI-ISI programs developed

after the RI-ISI methodology

has been endorsed i G 1.147, the staff anticipates

that the licensee will develop RH-ISI program using the approv ASME Code Cases and submit the program to NRC for information

with no formal NR approval.If you have any questions

bout the information

in this notice, please contact one of the technical

contacts liste elow or the appropriate

NRR project manager..Jack W. Roe, Acting Director Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical

ontacts: S. Ali, NRR W. Burton, NRR 301-415-2776

301-415-2853 E-mail: saa3@nrc.gov

E-mail: wfb@nrc.gov

Attac ment: List of Recently Issued NRC Information

Notices DOCUMENT NAME: G:\ALl\in

isi-2.wpd

k cr)V To receive a coDy of this document, indicate in the box C=Copy w/o attachr/eni/enclosure

E=Copy with attachment/enclosure

N = No copy OFFICE PECB I l (4 l l DE _ lL °R l l (A)D:DRPM

I lNAME WBurton* SAi* G as 1'GBagshi*

.o JStolz JRoe DATE 9/17/98 9/17/98 1i98 9/17/98 I/ l2M I /98 1 /98 OFFICIAL RECORD COPY 1* See Previous Concurrence

O RC ao JCr

IN 98-xx September

xx 1998 approved WOG or EPRI Topical Report as guidance for developing

RI-ISI programs.

The review and approval process is expected to be minimal when the submittal

follows the guidelines

in the approved Topical Report, NRC Regulatory

Guide 1.178, "An Appro;Kfor

Plant-Specific

Risk-informed

Decision making Inservice

Inspection

of Piping" a tandard Review Plan 3.9.8, "Standard

Review Plan for the Review of Risk-informed

ervice Inspection

of Piping".It is anticipated

that subsequent

to the issuance of safety evaluati reports (SER) for the pilot plants and the topical reports, the industry will revise the ASM ode Cases to incorporate

lessons learned from pilot plants and topical report reviews. e ASME Code Cases will be endorsed by RG 1.147, 'Inservice

Inspection

Code Case ceptability

-ASME Section Xi Division 1V, and subsequently

incorporated

into the AS E Code. In the long term, the staff will proceed with rulemaking

so that other licensees

can oluntarily

adopt risk-informed

ISI programs without specific NRC review and approv .For the RI-ISI programs developed

after the RI-ISI methodology

has been endorsed in 1.147, the staff anticipates

that the licensee will develop RI-ISI program using the approv ASME Code Cases and submit the program to NRC for information

with no formal NRC a roval.This information

notice requires no s cific action or written response.

However, recipients

are reminded that they are required b 0 CFR 50.65 to take industry-wide

operating

experience (including

information

presente NRC information

notices) into consideration

when setting goals and performing

periodi valuations.

If you have any questions

about the information

in this notice, please contact e of the technical

contacts listed below or the appropriate

NRR project manager.Jack W. Roe, Acting Director Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technica Contacts:

S. Ali, NRR W. Burton, NRR 301-415-2776

301-415-2853 E-mail: saa3@nrc.gov

E-mail: wfb~nrc.gov

Attachment:

List of Recently Issued NRC Information

Notices DOCUMENT NAME: G:\wfb\on-isi.wpd

To receive a copy of this document, indicate in the box C=Copy w/o attachmer(enclosure

E=Copy with attachmentlenclosure

N = No copy OFFICE PECB I E l (A)D:DEIQEl

OGC C:PECB I (A)D:DRPM

I NAME WBurtonA/4 SAIi W GLainas G g si JMoore JStolz JRoe 1 DATE 1117198 11198 _9/__98 / /98 / /98 I /98_ OFFICIAL REC RD COPy bA\WS'