Information Notice 1998-44, Ten-Year Inservice Inspection (ISI) Program Update for Licensees That Intend to Implement Risk-Informed ISI of Piping
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
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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
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Attachment
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-1Nl lopy
OFFICE
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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
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(A)D:DE lIC:ECGB LT
C:PECB I
(A)D:DRPM
NAME
WBurton*
SAli*
GLainas*
GBagchi*
JMoore*
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JRoe
11DATE
19/17198
19/17/98
19/29/98
19/17/98
111/26/98
/\\
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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
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DATE
9/17/98
9/17/98
1i98
9/17/98 I/ l2M
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1 /98 OFFICIAL RECORD COPY
1
- See Previous Concurrence
O
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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
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(A)D:DEIQEl
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
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