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

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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY
{{#Wiki_filter:UNITED STATES


COMMISSION
===NUCLEAR REGULATORY COMMISSION===
OFFICE OF NUCLEAR REACTOR REGULATION


===OFFICE OF NUCLEAR REACTOR REGULATION===
WASHINGTON, D.C. 20555-0001
WASHINGTON, D.C. 20555-0001 December 10, 1998 NRC INFORMATION


NOTICE 98-44: TEN-YEAR INSERVICE
===December 10, 1998===
NRC INFORMATION NOTICE 98-44: TEN-YEAR INSERVICE INSPECTION (ISI) PROGRAM


INSPECTION (ISI) PROGRAM UPDATE FOR LICENSEES
===UPDATE FOR LICENSEES THAT INTEND TO===
 
IMPLEMENT RISK-INFORMED ISI OF PIPING
THAT INTEND TO IMPLEMENT
 
RISK-INFORMED
 
ISI OF PIPING


==Addressees==
==Addressees==
All holders of operating
All holders of operating licenses for nuclear power reactors, except those that have
 
licenses for nuclear power reactors, except those that have permanently
 
ceased operations
 
and have certified


that fuel has been permanently
permanently ceased operations and have certified that fuel has been permanently removed


removed from the reactor.
from the reactor.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to inform


Commission (NRC) is issuing this information
addressees that for those licensees that intend to implement a risk-informed inservice


notice to inform addressees
inspection (RI-ISI) program for piping and do not have a pilot plant application currently being


that for those licensees
reviewed by the staff, the staff will consider authorizing a delay of up to 2 years in implementing


that intend to implement
the next 1 0-year ISI program for piping only in order for the licensee to develop and obtain


a risk-informed
approval for the RI-ISI program for piping.


inservice inspection (RI-ISI) program for piping and do not have a pilot plant application
It is expected that recipients will review this information for applicability to their facilities and


currently
consider actions, as appropriate. However, suggestions contained in this information notice are


being reviewed by the staff, the staff will consider authorizing
not NRC requirements; therefore, no specific action or written response is required.


a delay of up to 2 years in implementing
==Description of Circumstances==
On August 16, 1995, the NRC published a policy statement (60 FR 42622) on the use of


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
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


will review this information
should be increased to the extent supported by the state of the art in PRA methods and data


for applicability
and in a manner that complements the NRC's deterministic approach. To implement this


to their facilities
policy, the staff developed a PRA implementation plan, together with a timetable for developing


and consider actions, as appropriate.
regulatory guides (RGs) and standard review plans (SRPs), which describes an acceptable


However, suggestions
approach for assessing the nature and impact of changes by considering engineering issues


contained
and applying risk insights. A part of this effort involves developing an RG and the


in this information
corresponding SRP to provide guidance to power reactor licensees and the NRC staff on an


notice are not NRC requirements;
table approach for utilizing risk information to support requests for changes in the plant's
therefore, no specific action or written response is required.Description


of Circumstances
9812100046
4
'o


On August 16, 1995, the NRC published
q(OO


a policy statement
qwOlo


(60 FR 42622) on the use of probabilistic
9A


risk assessment (PRA) methods in nuclear regulatory
98-44 December 10, 1998 ISI program for piping. The draft documents were available for public comment through


activities.
January 13, 1998, and the staff revised the draft documents to incorporate public comments.


In the statement, the Commission
The RG and the SRP were issued for trial use on October 13, 1998.


stated its belief that the use of PRA technology
The nuclear industry has submitted two topical reports describing methodologies for


in NRC regulatory
implementing RI-ISI. One methodology has been jointly developed by the American Society of


activities
Mechanical Engineers (ASME) and the Westinghouse Owners Group (WOG). The other


should be increased
methodology is being sponsored by the Electric Power Research Institute (EPRI).


to the extent supported
In addition, ASME is working on three ASME Code cases for alternate examination


by the state of the art in PRA methods and data and in a manner that complements
requirements to ASME Section Xl, Division 1, for piping welds. ASME Code Case N-577 is


the NRC's deterministic
based on the WOG methodology and ASME Code Case N-578 is based on the EPRI


approach.
methodology. ASME Code Case N-560 is based on the EPRI methodology for Class 1 B-J


To implement
welds and is being revised to encompass both methodologies.


this policy, the staff developed
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


a PRA implementation
in systems scheduled for ISI. The NRC has completed its review of the pilot plant submittal for


plan, together with a timetable
Vermont Yankee and is currently reviewing the submittals for Surry Unit 1 and Arkansas


for developing
Nuclear One, Units I and 2, focusing on the licensees' characterization of the proposed


regulatory
changes, including identification of the particular piping systems and welds that are affected by


guides (RGs) and standard review plans (SRPs), which describes
the changes, the performance of engineering evaluations, the performance of PRAs to provide


an acceptable
risk insight to support the selection of welds for inspection, the performance of traditional


approach for assessing
engineering analyses to verify that the proposed changes do not compromise the existing


the nature and impact of changes by considering
regulations and the licensing basis of the plant, the development of implementation and


engineering
monitoring programs to ensure that the reliability of piping can be maintained, and the


issues and applying risk insights.
documentation of the analyses for NRC's review and approval. The staff will use the alternative


A part of this effort involves developing
provision of 10 CFR 50.55a (a)(3)(1) to approve technically acceptable pilot plant applications.


an RG and the corresponding
Discussion


SRP to provide guidance to power reactor licensees
For non-pilot plant licensees that intend to implement RI-ISI beginning with their next 10-year


and the NRC staff on an table approach for utilizing
interval, the staff will consider authorizing a delay of up to 2 years in the implementation of the


risk information
next 1 0-year ISI program for piping only to allow licensees to develop and obtain approval for


to support requests for changes in the plant's 9812100046
their RI-ISI program at the next available opportunity using the staff-approved topical reports.
4 'o q(OO qwOlo 9A


98-44 December 10, 1998 ISI program for piping. The draft documents
For those licensees that are authorized such a delay, the approved RI-ISI program would have


were available
to be completed within the remaining part of the 10-year interval, for example, programs would


for public comment through January 13, 1998, and the staff revised the draft documents
be shortened to 8 years for a 2-year delay. The duration of the delay needed may vary


to incorporate
according to individual cases. Therefore, the request for delay must provide adequate


public comments.The RG and the SRP were issued for trial use on October 13, 1998.The nuclear industry has submitted
justification, along with a clear indication of the inspection that will continue before the


two topical reports describing
implementation of the RI-ISI program. During the delay period, licensees would be required to


methodologies
continue augmented inspection programs, such as inspections for intergranular stress-corrosion


for implementing
cracking and erosion-corrosion, inspections required for flaws dispositioned by analysis, system


RI-ISI. One methodology
pressure tests, and inspection of components other than piping.


has been jointly developed
',_98-44 December 10, 1998 The staff plans to perform in-depth reviews of pilot plant submittals during 1998 and 1999 to


by the American Society of Mechanical
ensure that the RI-ISI programs are consistent with the staff RG and SRP. For RI-ISI programs


Engineers (ASME) and the Westinghouse
submitted after the approval of the pilot plant programs and topical reports, but before the


Owners Group (WOG). The other methodology
endorsement of ASME Code cases, it Is expected that licensees will utilize the approved WOG


is being sponsored
or EPRI topical report as guidance for developing RI-ISI programs. The review and approval


by the Electric Power Research Institute (EPRI).In addition, ASME is working on three ASME Code cases for alternate
process is expected to be minimal when the submittal follows the guidelines in the approved


examination
topical report, NRC Regulatory Guide 1.178, wAn Approach for Plant-Specific Risk-informed


requirements
Decisionmaking Inservice Inspection of Piping"; Standard Review Plan 3.9.8, Standard Review


to ASME Section Xl, Division 1, for piping welds. ASME Code Case N-577 is based on the WOG methodology
Plan for the Review of Risk-Informed Inservice Inspection of Piping"; and the safety evaluation


and ASME Code Case N-578 is based on the EPRI methodology.
reports for the applicable topical report.


ASME Code Case N-560 is based on the EPRI methodology
It is anticipated that subsequent to the issuance of safety evaluation reports (SERs) for the pilot


for Class 1 B-J welds and is being revised to encompass
plants and the topical reports, the ASME Code cases will be revised to incorporate lessons


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


The NRC has encouraged
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


licensees
proceed with rulemaking so that other licensees can voluntarily adopt risk-informed ISI


to submit pilot plant applications
programs without specific review and approval by NRC. For the RI-ISI programs developed


for demonstrating
after the an RI-ISI methodology has been endorsed in RG 1.147, the staff anticipates that the


risk-informed methodologies
licensee will develop an RI-ISI program using the approved ASME Code cases and will submit


to be used for piping segment and piping structural
the program to NRC for information with no formal NRC approval.


element selection in systems scheduled
If you have any questions about the information in this notice, please contact one of the


for ISI. The NRC has completed
technical contacts listed below or the appropriate NRR project manager.


its review of the pilot plant submittal
( d/Jack W. Roe, Acting Director


for Vermont Yankee and is currently
===Division of Reactor Program Management===
Office of Nuclear Reactor Regulation


reviewing
Technical Contacts:
S. Ali, NRR


the submittals
===W. Burton, NRR===
301-415-2776
301-415-2853 E-mail: saa3@nrc.gov


for Surry Unit 1 and Arkansas Nuclear One, Units I and 2, focusing on the licensees'
E-mail: wfb@nrc.gov
characterization


of the proposed changes, including
Attachment:


identification
===List of Recently Issued NRC Information Notices===
4aF4S


of the particular
4 JA4OT,


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


of engineering
IN 98-44


evaluations, the performance
===December 10, 1998 LIST OF RECENTLY ISSUED===
NRC INFORMATION NOTICES


of PRAs to provide risk insight to support the selection
Information


of welds for inspection, the performance
Date of


of traditional
Notice No.


engineering
Subject


analyses to verify that the proposed changes do not compromise
Issuance


the existing regulations
Issued to


and the licensing
98-43


basis of the plant, the development
===Leaks in the Emergency Diesel===
Generator Lubricating Oil and


of implementation
===Jacket Cooling Water Piping===
12/04/98


and monitoring
===All holder of operating licenses===
for nuclear power reactors, except


programs to ensure that the reliability
those licensees that have


of piping can be maintained, and the documentation
permanently ceased operations


of the analyses for NRC's review and approval.
and have certified that fuel has


===The staff will use the alternative===
been permanently removed from
provision


of 10 CFR 50.55a (a)(3)(1)
the reactor vessel
to approve technically


acceptable
98-42 Implementation of 10 CFR 50.55a


pilot plant applications.
12/01/98 (g) Inservice Inspection Requirements


Discussion
Spurious Shutdown of Emergency


For non-pilot
11/20/98


plant licensees
===Diesel Generators from Design===
Oversight


that intend to implement
98-41
98-40


RI-ISI beginning
===Design Deficiencies Can Lead===
Reduced ECCS Pump Net Positive


with their next 10-year interval, the staff will consider authorizing
Suction Head During Design-Basis


a delay of up to 2 years in the implementation
Accidents


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


to develop and obtain approval for their RI-ISI program at the next available
===Program Performance Reports for===
Calendar Years 1996 and 1997 Metal-Clad Circuit Breaker


opportunity
===Maintenance Issued Identified===
 
By NRC Inspections
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
10/26/98
10/24/98
10/15/98


with the staff RG and SRP. For RI-ISI programs submitted
===All holders of operating licenses===
for nuclear power reactors


after the approval of the pilot plant programs and topical reports, but before the endorsement
===All holders of operating licenses===
for nuclear power reactors, except


of ASME Code cases, it Is expected that licensees
for those who have ceased


will utilize the approved WOG or EPRI topical report as guidance for developing
operations and have certified that


RI-ISI programs.
fuel has been permanently


The review and approval process is expected to be minimal when the submittal
removed from the reactor vessel


follows the guidelines
===All holders of operating licenses===
for nuclear power reactors, except


in the approved topical report, NRC Regulatory
those licensees who have


Guide 1.178, wAn Approach for Plant-Specific
permanently ceased operations


Risk-informed
and have certified that fuel has


Decisionmaking
bee permanently removed from


Inservice
the vessel


Inspection
===All holders of operating licenses===
for nuclear power reactors


of Piping"; Standard Review Plan 3.9.8, Standard Review Plan for the Review of Risk-Informed
===All holders of operating licenses===
for nuclear power reactors.


Inservice
98-39
98-38 OL = Operating License


Inspection
CP = Construction Permit


of Piping"; and the safety evaluation
`n4 98-44 December 10, 1998 The staff plans to perform in-depth reviews of pilot plant submittals during 1998 and 1999 to


reports for the applicable
ensure that the RI-ISI programs are consistent with the staff RG and SRP. For RI-ISI programs


topical report.It is anticipated
submitted after the approval of the pilot plant programs and topical reports, but before the


that subsequent
endorsement of ASME Code cases, it is expected that licensees will utilize the approved WOG


to the issuance of safety evaluation
or EPRI topical report as guidance for developing RI-ISI programs. The review and approval


reports (SERs) for the pilot plants and the topical reports, the ASME Code cases will be revised to incorporate
process is expected to be minimal when the submittal follows the guidelines in the approved


lessons learned from pilot plants and topical report reviews. The ASME Code cases will be reviewed in accordance
topical report, NRC Regulatory Guide 1.178, "An Approach for Plant-Specific Risk-informed


with RG 1.147, Oinservice
Decisionmaking Inservice Inspection of Piping"; Standard Review Plan 3.9.8, "Standard Review


Inspection
Plan for the Review of Risk-Informed Inservice Inspection of Piping"; and the safety evaluation


Code Case Acceptability
reports for the applicable topical report.


-ASME Section Xi, Division 1," for possible incorporation
It is anticipated that subsequent to the issuance of safety evaluation reports (SERs) for the pilot


into the ASME Code. In the long term, the staff will proceed with rulemaking
plants and the topical reports, the ASME Code cases will be revised to incorporate lessons


so that other licensees
learned from pilot plants and topical report reviews. The ASME Code cases will be reviewed in


can voluntarily
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


adopt risk-informed
proceed with rulemaking so that other licensees can voluntarily adopt risk-informed ISI


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


has been endorsed in RG 1.147, the staff anticipates
after the RI-ISI methodology has been endorsed in RG 1.147, the staff anticipates that the


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


with no formal NRC approval.If you have any questions
the program to NRC for information with no formal NRC approval.


about the information
If you have any questions about the information in this notice, please contact one of the


in this notice, please contact one of the technical
technical contacts listed below or the appropriate NRR project manager.


contacts listed below or the appropriate
[original signed by D.B. Matthews]
f or


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


===Office of Nuclear Reactor Regulation===
===Office of Nuclear Reactor Regulation===
Technical
Technical Contacts:
S. Ali, NRR


Contacts:
===W. Burton, NRR===
S. Ali, NRR W. Burton, NRR 301-415-2776  
301-415-2776  
301-415-2853 E-mail: saa3@nrc.gov
301-415-2853 E-mail: saa3@nrc.gov


E-mail: wfb@nrc.gov
E-mail: wfb~nrc.gov


Attachment:  
Attachment:  
List of Recently Issued NRC Information


Notices 4aF4S 4 JA4OT,
===List of Recently Issued NRC Information Notices===
\, Attachment
DOCUMENT NAME: G:\\ALI\\INISI.WPD


IN 98-44 December 10, 1998 LIST OF RECENTLY ISSUED NRC INFORMATION
* See Previous Concurrence
 
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
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


License CP = Construction
OFFICE


Permit
PECB


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


during 1998 and 1999 to ensure that the RI-ISI programs are consistent
(A)D:DE


with the staff RG and SRP. For RI-ISI programs submitted
I C:ECG


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


of ASME Code cases, it is expected that licensees
[ l


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


RI-ISI programs.
(A


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


follows the guidelines
WBurton* . SAIi*
GLainas*
GBagchi*
JMoore*
JStolz*
J


in the approved topical report, NRC Regulatory
VJ


Guide 1.178, "An Approach for Plant-Specific
DATE


Risk-informed
j 9/17/98
9/17/98 j 9/29/98
9/17/98
11/26/98
12/04/98
1XI /198


Decisionmaking
===OFFICIAL RECORD COPY===


Inservice
T'N 98-xx


Inspection
December xx, 1998 The staff plans to perform in-depth reviews of pilot plant submittals during 1998 and 1999 to


of Piping"; Standard Review Plan 3.9.8, "Standard
ensure that the RI-ISI programs are consistent with the staff RG and SRP. For RI-ISI programs


Review Plan for the Review of Risk-Informed
submitted after the approval of the pilot plant programs and topical reports, but before the


Inservice
endorsement of ASME Code cases, it is expected that licensees will utilize the approved WOG


Inspection
or EPRI topical report as guidance for developing RI-ISI programs. The review and aX


of Piping"; and the safety evaluation
val


reports for the applicable
process is expected to be minimal when the submittal follows the guidelines in th


topical report.It is anticipated
pproved


that subsequent
topical report, NRC Regulatory Guide 1.178, "An Approach for Plant-Specificgsk-lnformed


to the issuance of safety evaluation
Decisionmaking Inservice Inspection of Piping"; Standard Review Plan 3.., "Standard Review


reports (SERs) for the pilot plants and the topical reports, the ASME Code cases will be revised to incorporate
Plan for the Review of Risk-informed Inservice Inspection of Piping";
d the safety evaluation


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


with RG 1.147, "Inservice
It is anticipated that subsequent to the issuance of safety eva tion reports (SERs) for the pilot


Inspection
plants and the topical reports, the ASME Code cases will bI revised to incorporate lessons


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


-ASME Section Xl, Division 11," for possible incorporation
accordance with RG 1.147, "Inservice Inspection Cod case Acceptability - ASME Section Xl, Division 1," for possible incorporation into the ASM


into the ASME Code. In the long term, the staff will proceed with rulemaking
===Code. In the long term, the staff will===
proceed with rulemaking so that other licensees


so that other licensees
voluntarily adopt risk-informed ISI


can voluntarily
programs without specific review and approval


adopt risk-informed
NRC. For the RI-ISI programs developed


ISI programs without specific review and approval by NRC. For the RI-ISI programs developed after the RI-ISI methodology
after the RI-ISI methodology has been endord in RG 1.147, the staff anticipates that the


has been endorsed in RG 1.147, the staff anticipates
licensee will develop an RI-ISI program usi


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


with no formal NRC approval.If you have any questions
the program to NRC for information with


about the information
formal NRC approval.


in this notice, please contact one of the technical
If you have any questions about the i ormation in this notice, please contact one of the


contacts listed below or the appropriate
technical contacts listed below or t


NRR project manager.[original
appropriate NRR project manager.


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


===Office of Nuclear Reactor Regulation===
===Office of Nuclear Reactor Regulation===
Technical
Technical Contacts:
S. Ali, NRR


Contacts:
===W. Burton, NRR===
S. Ali, NRR W. Burton, NRR 301-415-2776  
301-415-2776  
301-415-2853 E-mail: saa3@nrc.gov
301-415-2853 E-mail: saa3@nrc.gov


E-mail: wfb~nrc.gov
E-mail: wfb~nrc.gov


Attachment:  
Attachment: List of Recently Issued NRC Information Notices
List of Recently Issued NRC Information


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


* See Previous Concurrence
T NAME: G:\\ALI\\IN ISI.WPD


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


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


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
OFFICE


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


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


with the staff RG and SRP. For RI-ISI programs submitted
(A)D:DE lIC:ECGB LT


after the approval of the pilot plant programs and topical reports, but before the endorsement
C:PECB I


of ASME Code cases, it is expected that licensees
(A)D:DRPM


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


RI-ISI programs.
WBurton*
SAli*
GLainas*
GBagchi*
JMoore*
JfpI


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


follows the guidelines
11DATE


in th pproved topical report, NRC Regulatory
19/17198
19/17/98
19/29/98
19/17/98
111/26/98
/\\
'/Ii~ / /98l


Guide 1.178, "An Approach for Plant-Specificgsk-lnformed
OFFICIAL RECORD COPY


Decisionmaking
V


Inservice
DATE /17/9
9/1798
9/9/98
/17/9
11/2/98
/ 9


Inspection
IN 98-xx


of Piping"; Standard Review Plan 3.., "Standard
October xx 1998 The staff plans to perform in-depth reviews of pilot plant submittals during 1998 and 1999 to


Review Plan for the Review of Risk-informed
ensure that the RI-ISI programs are consistent with the staff RG and SRP. For RI-ISI programs


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


Inspection
endorsement of ASME Code Cases, it is expected that licensees will utilize


of Piping"; d the safety evaluation
approved WOG


reports for the applicable
or EPRI Topical Report as guidance for developing RI-ISI programs. TW review and approval


topical report.It is anticipated
process is expected to be minimal when the submittal follows the gu


that subsequent
lines in the approved


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
Topical Report, NRC Regulatory Guide 1.178, 'An Approach for P nt-Specific Risk-Informed


lessons learned from pilot plants and topical report reviews. The SME Code cases will be reviewed in accordance
Decision making Inservice Inspection of Piping", Standard Rev idw Plan 3.9.8, 'Standard Review


with RG 1.147, "Inservice
Plan for the Review of Risk-Informed Inservice Inspection o 5iping", and the safety evaluation


Inspection
reports for the applicable topical report.


Cod case Acceptability
It is anticipated that subsequent to the issuance of s


-ASME Section Xl, Division 1," for possible incorporation
ety evaluation reports (SER) for the pilot


into the ASM Code. In the long term, the staff will proceed with rulemaking
plants and the topical reports, the industry will rev' e the ASME Code Cases to incorporate


so that other licensees
lessons learned from pilot plants and topical re


voluntarily
rt reviews. The ASME Code Cases will be


adopt risk-informed
endorsed by RG 1.147, "Inservice Inspectio


ISI programs without specific review and approval NRC. For the RI-ISI programs developed after the RI-ISI methodology
ode Case Acceptability - ASME Section Xl


has been endord in RG 1.147, the staff anticipates
Division 1," and subsequently incorporate into the ASME Code. In the long term, the staff will


that the licensee will develop an RI-ISI program usi the approved ASME Code cases and will submit the program to NRC for information
proceed with rulemaking so that other Ii


with formal NRC approval.If you have any questions
nsees can voluntarily adopt risk-informed ISI programs


about the i ormation in this notice, please contact one of the technical
without specific NRC review and app val. For the RI-ISI programs developed after the RI-ISI


contacts listed below or t appropriate
methodology has been endorsed i


NRR project manager.Jack W. Roe, Acting Director Division of Reactor Program Management
G 1.147, the staff anticipates that the licensee will develop


===Office of Nuclear Reactor Regulation===
RH-ISI program using the approv
Technical


Contacts:
===ASME Code Cases and submit the program to NRC for===
S. Ali, NRR W. Burton, NRR 301-415-2776
information with no formal NR approval.
301-415-2853 E-mail: saa3@nrc.gov


E-mail: wfb~nrc.gov
If you have any questions bout the information in this notice, please contact one of the


Attachment:
technical contacts liste
List of Recently Issued NRC Information


Notices DOCUMW T NAME: G:\ALI\IN
elow or the appropriate NRR project manager..


ISI.WPD* See P vious Concurrence
===Jack W. Roe, Acting Director===
Division of Reactor Program Management


To receive a copy of this document, indicate in the box C=Copy wlo attachment/enclosure
===Office of Nuclear Reactor Regulation===
Technical ontacts:
S. Ali, NRR


E=Copy with attachmentlenclosure
===W. Burton, NRR===
301-415-2776
301-415-2853 E-mail: saa3@nrc.gov


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
E-mail: wfb@nrc.gov
/\ '/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
Attac ment:


with the staff RG and SRP. For RI-ISI programs submitted
===List of Recently Issued NRC Information Notices===
DOCUMENT NAME: G:\\ALl\\in isi-2.wpd k cr)V


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


of ASME Code Cases, it is expected that licensees
OFFICE


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


RI-ISI programs.
I l


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


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


Guide 1.178, 'An Approach for P nt-Specific
_
lL


Risk-Informed
°R


Decision making Inservice
l


Inspection
l


of Piping", Standard Rev idw Plan 3.9.8, 'Standard
(A)D:DRPM I l


Review Plan for the Review of Risk-Informed
NAME


Inservice
WBurton*
SAi*
G


Inspection
as


o 5iping", and the safety evaluation
1'GBagshi*
.o


reports for the applicable
JStolz


topical report.It is anticipated
JRoe


that subsequent
DATE


to the issuance of s ety evaluation
9/17/98
9/17/98
1i98
9/17/98 I/ l2M


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


lessons learned from pilot plants and topical re rt reviews. The ASME Code Cases will be endorsed by RG 1.147, "Inservice
/98
1 /98 OFFICIAL RECORD COPY


Inspectio
1
* See Previous Concurrence


ode Case Acceptability
O


-ASME Section Xl Division 1," and subsequently
RC


incorporate
ao JCr


into the ASME Code. In the long term, the staff will proceed with rulemaking
IN 98-xx


so that other Ii nsees can voluntarily
September xx 1998 approved WOG or EPRI Topical Report as guidance for developing RI-ISI programs. The


adopt risk-informed
review and approval process is expected to be minimal when the submittal follows the


ISI programs without specific NRC review and app val. For the RI-ISI programs developed
guidelines in the approved Topical Report, NRC Regulatory Guide 1.178, "An Appro;Kfor


after the RI-ISI methodology
Plant-Specific Risk-informed Decision making Inservice Inspection of Piping" a


has been endorsed i G 1.147, the staff anticipates
tandard


that the licensee will develop RH-ISI program using the approv ASME Code Cases and submit the program to NRC for information
Review Plan 3.9.8, "Standard Review Plan for the Review of Risk-informed


with no formal NR approval.If you have any questions
ervice Inspection
 
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
of Piping".


===Office of Nuclear Reactor Regulation===
It is anticipated that subsequent to the issuance of safety evaluati
Technical


ontacts: S. Ali, NRR W. Burton, NRR 301-415-2776
reports (SER) for the pilot
301-415-2853 E-mail: saa3@nrc.gov


E-mail: wfb@nrc.gov
plants and the topical reports, the industry will revise the ASM


Attac ment: List of Recently Issued NRC Information
ode Cases to incorporate


Notices DOCUMENT NAME: G:\ALl\in
lessons learned from pilot plants and topical report reviews.


isi-2.wpd
e ASME Code Cases will be


k cr)V To receive a coDy of this document, indicate in the box C=Copy w/o attachr/eni/enclosure
endorsed by RG 1.147, 'Inservice Inspection Code Case ceptability - ASME Section Xi


E=Copy with attachment/enclosure
Division 1V, and subsequently incorporated into the AS E Code. In the long term, the staff will


N = No copy OFFICE PECB I l (4 l l DE _ lL °R l l (A)D:DRPM
proceed with rulemaking so that other licensees can oluntarily adopt risk-informed ISI


I lNAME WBurton* SAi* G as 1'GBagshi*
programs without specific NRC review and approv . For the RI-ISI programs developed after
.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
the RI-ISI methodology has been endorsed in


IN 98-xx September
1.147, the staff anticipates that the licensee


xx 1998 approved WOG or EPRI Topical Report as guidance for developing
will develop RI-ISI program using the approv


RI-ISI programs.
===ASME Code Cases and submit the program to===
NRC for information with no formal NRC a


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


follows the guidelines
This information notice requires no s cific action or written response. However, recipients are


in the approved Topical Report, NRC Regulatory
reminded that they are required b


Guide 1.178, "An Appro;Kfor
0 CFR 50.65 to take industry-wide operating experience


Plant-Specific
(including information presente


Risk-informed
NRC information notices) into consideration when setting


Decision making Inservice
goals and performing periodi


Inspection
valuations. If you have any questions about the information in


of Piping" a tandard Review Plan 3.9.8, "Standard
this notice, please contact


Review Plan for the Review of Risk-informed
e of the technical contacts listed below or the appropriate NRR


ervice Inspection
project manager.


of Piping".It is anticipated
===Jack W. Roe, Acting Director===
Division of Reactor Program Management


that subsequent
===Office of Nuclear Reactor Regulation===
Technica Contacts:
S. Ali, NRR


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
===W. Burton, NRR===
301-415-2776
301-415-2853 E-mail: saa3@nrc.gov


lessons learned from pilot plants and topical report reviews. e ASME Code Cases will be endorsed by RG 1.147, 'Inservice
E-mail: wfb~nrc.gov


Inspection
Attachment:
 
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
===List of Recently Issued NRC Information Notices===
DOCUMENT NAME: G:\\wfb\\on-isi.wpd


are reminded that they are required b 0 CFR 50.65 to take industry-wide
To receive a copy of this document, indicate in the box C=Copy w/o attachmer(enclosure E=Copy with attachmentlenclosure N = No copy


operating
OFFICE


experience (including
PECB


information
I


presente NRC information
E


notices) into consideration
l


when setting goals and performing
(A)D:DEIQEl


periodi valuations.
OGC


If you have any questions
C:PECB I


about the information
(A)D:DRPM I


in this notice, please contact e of the technical
NAME


contacts listed below or the appropriate
WBurtonA/4 SAIi W


NRR project manager.Jack W. Roe, Acting Director Division of Reactor Program Management
GLainas
 
===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
G g si


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


E=Copy with attachmentlenclosure
JStolz


N = No copy OFFICE PECB I E l (A)D:DEIQEl
JRoe 1 DATE


OGC C:PECB I (A)D:DRPM
1117198
11198
_9/__98
/ /98
/ /98 I /98
_ OFFICIAL REC RD COPy


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'}}
bA\\WS'}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 11:59, 16 January 2025

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)
v • d • e


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-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

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 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

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'


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