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, 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:	12/10/1998
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 10-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 'o 4 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 10-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 12/04/98 All holder of operating licenses

Generator Lubricating Oil and for nuclear power reactors, except

Jacket Cooling Water Piping 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 All holders of operating licenses

(g) Inservice Inspection Requirements for nuclear power reactors

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 10/24/98 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

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-1Nl 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

DATE9/1798

/17/9 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 l l (4 DE lL_ °R l l (A)D:DRPM I l

NAME 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

NAME

DATE

PECB

1117198 I

WBurtonA/4 SAIi W

E

11198 l (A)D:DEIQEl

GLainas

_9/__98 G g si

OGC

JMoore

/ /98 C:PECB I

JStolz

/ /98 (A)D:DRPM I

JRoe

I /98

1

_ OFFICIAL REC RD COPy

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