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{{#Wiki_filter:UNITED STATES NUCLEAR REGULA TORY COMMISSION | {{#Wiki_filter:NYS000310 | ||
OFFICE OF NUCLEAR REACTOR REGULATION | Submitted: December 22, 2011 | ||
WASHINGTON, DC 20555-0001 | UNITED STATES | ||
July 21, 2011 NRC REGULATORY | NUCLEAR REGULA TORY COMMISSION | ||
ISSUE SUMMARY 2011-07 LICENSE RENEWAL SUBMITTAL | OFFICE OF NUCLEAR REACTOR REGULATION | ||
INFORMATION | WASHINGTON, DC 20555-0001 | ||
July 21, 2011 | |||
WATER REACTOR INTERNALS | NRC REGULATORY ISSUE SUMMARY 2011-07 | ||
AGING MANAGEMENT | LICENSE RENEWAL SUBMITTAL INFORMATION FOR | ||
ADDRESSEES | PRESSURIZED WATER REACTOR INTERNALS AGING MANAGEMENT | ||
All holders of and applicants | ADDRESSEES | ||
for a pressurized | All holders of and applicants for a pressurized water power reactor operating license or | ||
water power reactor operating | construction permit under Title 10 of the Code of Federal Regulations (10 CFR) Part 50, | ||
license or construction | "Domestic Licensing of Production and Utilization Facilities," except those that have | ||
permit under Title 10 of the Code of Federal Regulations | permanently ceased operations and have certified that fuel has been permanently removed | ||
(10 CFR) Part 50, "Domestic | from the reactor vessel. | ||
Licensing | INTENT | ||
of Production | The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) | ||
and Utilization | to inform addressees of updated NRC procedures for license renewal application (LRA) reviews | ||
Facilities," except those | or the review of certain licensee submittals related to commitments made in the process of | ||
that have permanently | receiving a renewed license. LRAs for pressurized water reactor (PWR) plants have identified | ||
ceased operations | that an aging management program (AMP) is needed to manage the effects of aging for reactor | ||
and have certified | vessel internal (RVI) components that are within the scope of license renewal, in accordance | ||
that fuel has been permanently | with 10 CFR Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power | ||
Plants." This RIS requires no action or written response on the part of addressees. This RIS | |||
Commission (NRC) is issuing this | also provides information to licensees with respect to how to meet their existing license renewal | ||
regulatory | commitments related to reactor vessel internals aging management programs, and on | ||
issue summary (RIS) to inform addressees | acceptable changes to existing license renewal commitments in order to account for the recent | ||
of updated NRC procedures | issue of the staff's final Safety Evaluation (SE) of MRP-227, Rev.O, and the forthcoming issue of | ||
for license renewal application (LRA) reviews or the review of certain licensee submittals | the approved version of MRP-227. | ||
related to commitments | The purpose of this RIS is to facilitate a predictable and consistent method for reviewing the | ||
made in the process of receiving | AMPs of commercial PWR LRAs and the AMPs and inspection plans for PWR plants that have | ||
a renewed license. LRAs for pressurized | received renewed operating licenses. This RIS does not transmit or imply any new or changed | ||
water reactor (PWR) plants have identified | requirements or staff positions. Although no specific action or written response is required, the | ||
that an aging management | information contained in this RIS will enable licensees to plan effectively for anticipated LRAs | ||
program (AMP) is needed to manage the effects of aging for reactor vessel internal (RVI) components | and inspection activities. | ||
that are within the scope of license renewal, in accordance | This RIS is part of the NRC's ongoing oversight of license renewal and is unrelated to the | ||
with 10 CFR Part 54, "Requirements | agency's response to the March 11, 2011, earthquake in Japan. | ||
for Renewal of Operating | ML 111990086 | ||
Licenses for Nuclear Power Plants." This RIS requires no action or written response on the part of addressees. | OAGI0001161 00001 | ||
This RIS also provides information | |||
to licensees | RIS 2011-07 | ||
with respect to how to meet their existing license renewal commitments | Page 2 of 7 | ||
related to reactor vessel internals | BACKGROUND INFORMATION | ||
aging management | In 10 CFR Part 54, the NRC addresses the requirements for plant LRAs. The regulation in | ||
programs, and on acceptable | 10 CFR 54.21, "Contents of Application-Technical Information," requires that each LRA | ||
changes to existing license renewal commitments | contain an integrated plant assessment and an evaluation of time-limited aging analyses. The | ||
in order to account for the recent issue of the staff's final Safety Evaluation (SE) of MRP-227, Rev.O, and the forthcoming | integrated plant assessment must identify and list those structures and components subject to | ||
issue of the approved version of MRP-227. The purpose of this RIS is to facilitate | an aging management review (AMR) and must demonstrate that the effects of aging (such as | ||
a predictable | cracking, loss of material, loss of fracture toughness, dimensional changes, and loss of preload) | ||
and consistent | will be adequately managed so that the intended functions of the structures and components will | ||
method for reviewing | be maintained consistent with the current licensing basis for the period of extended operation as | ||
required by 10 CFR 54.29(a). Structures and components subject to an AMR shall encompass | |||
PWR LRAs and the AMPs and inspection | those structures and components (1) that perform an intended function, as described in | ||
plans for PWR plants that have received renewed operating | 10 CFR 54.4, "Scope," without moving parts or without a change in configuration or properties, | ||
licenses. | and (2) that are not subject to replacement based on a qualified life or specified time period. | ||
This RIS does not transmit or imply any new or changed requirements | These structures and components are referred to as "passive" and "long-lived," respectively. | ||
or staff positions. | On April 26, 2001, the NRC issued N UREG-1801, "Generic Aging Lessons Learned (GALL) | ||
Although no specific action or written response is required, the information | Report," (Agencywide Documents Access and Management System (ADAMS) Accession Nos. | ||
contained | ML011080185 and ML011080393). On September 30, 2005, the NRC issued NUREG-1801, | ||
in this RIS will enable licensees | Revision 1, "Generic Aging Lessons Learned (GALL) Report," (ADAMS Accession Nos. | ||
to plan effectively | ML052770419 and ML052780376). On December 31, 2010, the NRC issued NUREG-1801, | ||
for anticipated | Revision 2, "Generic Aging Lessons Learned (GALL) Report," (ADAMS Accession No. | ||
ML 103490041). The GALL Report provides generic AMRs of systems, structures, and | |||
activities. | components that are within the scope of license renewal, as described in 10 CFR 54.4, and | ||
This RIS is part of the NRC's ongoing oversight | provides generic AMPs that the staff has found acceptable to manage the effects of aging | ||
of license renewal and is unrelated | identified in the AMR. As described in NUREG-1800, Revision 2, "Standard Review Plan for | ||
to the agency's response to the March 11, 2011, earthquake | Review of License Renewal Applications for Nuclear Power Plants" (ADAMS Accession No. | ||
in Japan. ML 111990086 | ML 103490036) (LR-SRP), treatment of the GALL Report as an approved topical report | ||
OAGI0001161 | improves the efficiency of the license renewal process. | ||
00001 | An applicant may reference in its LRA that its AMPs are consistent with those in the GALL | ||
Report. If an applicant takes credit for an AMP in the GALL Report, it is incumbent on the | |||
applicant to ensure that the conditions and operating experience at the plant are bounded by | |||
RIS 2011-07 Page 2 of 7 In 10 CFR Part 54, the NRC addresses | those for which the AMP in the GALL Report was evaluated and found acceptable. In such a | ||
the requirements | case, the NRC staff's review of the AMP is limited to verifying that the applicant's AMP is | ||
for plant LRAs. The regulation | consistent with that provided in the GALL Report, including the conditions and operating | ||
experience provided in the GALL Report. | |||
of Application- | If the applicant's conditions and operating experience are not bounded by those of the GALL | ||
Technical | Report AMP, it is incumbent on the applicant to address the additional effects of aging that may | ||
Information," requires that each LRA contain an integrated | apply to the applicant's facility and supplement the GALL Report AMR line items and AMPs as | ||
plant assessment | necessary. The staff's review then addresses the acceptability of the AMR and the AMPs to be | ||
and an evaluation | used by the applicant. | ||
of time-limited | Revision 1 of the GALL Report provides AMP XI.M16, "PWR Vessel Internals," which refers to | ||
aging analyses. | the aging management guidance of the AMR line items for RVI components. Within the context | ||
OAGI0001161 00002 | |||
plant assessment | |||
must identify and list those structures | RIS 2011-07 | ||
and components | Page 3 of 7 | ||
subject to an aging management | of this RIS, NRC license renewals, theSE for MRP-227 and other NRC licensing actions, "RVI" | ||
review (AMR) and must demonstrate | refers to reactor vessel internals. In recognition that the industry was conducting programs to | ||
that the effects of aging (such as cracking, loss of material, loss of fracture toughness, dimensional | investigate aging of RVI components and to develop aging management guidelines for RVI | ||
changes, and loss of preload) will be adequately | components, the AMR line items for RVI components state that: | ||
managed so that the intended functions | No further aging management review is necessary if the applicant provides a | ||
of the structures | commitment in the FSAR [final safety analysis report] supplement to (1) participate in the | ||
and components | industry programs for investigating and managing aging effects on reactor internals; (2) | ||
evaluate and implement the results of the industry programs as applicable to the reactor | |||
consistent | internals; and (3) upon completion of these programs, but not less than 24 months | ||
with the current licensing | before entering the period of extended operation, submit an inspection plan for reactor | ||
basis for the period of extended operation | internals to the NRC for review and approval. | ||
Each licensee that made a commitment to conform to GALL AMP XI.M16, or an equivalent | |||
Structures | commitment under the 2001 GALL Report, also made a commitment in its FSAR supplement | ||
and components | that it will implement a plant-specific AMP for its RVI components based on the industry- | ||
subject to an AMR shall encompass | developed guidance. | ||
those structures | On January 12, 2009, the Electric Power Research Institute (EPRI) submitted for NRC staff | ||
and components | review and approval the Materials Reliability Program (MRP) Report 1016596 (MRP-227), | ||
(1) that perform an intended function, as described | Revision 0, "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines" | ||
(ADAMS Accession No. ML090160204). MRP-227 is the industry-developed guidance that | |||
or properties, and (2) that are not subject to replacement | licensees will use to develop their plant-specific AMP for RVI components. MRP-227, | ||
based on a qualified | Revision 0 contains a discussion of the technical basis for the development of plant-specific | ||
life or specified | AMPs for RVI components in PWR vessels. MRP-227, Revision 0 also provides inspection and | ||
time period. These structures | evaluation guidelines for PWR licensees to use in their plant-specific AMPs. Once approved by | ||
and components | the NRC, MRP-227 will provide the basis for renewed license holders to develop plant-specific | ||
are referred to as "passive" and "long-lived," respectively. | inspection plans to manage aging effects on RVI components, as described by their FSAR | ||
On April 26, 2001, the NRC issued N | commitment. | ||
Documents | The scope of components considered for inspection under the guidance of MRP-227, | ||
Access and Management | Revision 0 includes core support structures (typically denoted as Examination Category B-N-3 | ||
System (ADAMS) Accession | by Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel | ||
Nos. ML011080185 | Code), and those RVI components that serve an intended safety function consistent with the | ||
and ML011080393). | criteria in 10 CFR 54.4(a)(1). The scope of the program does not include consumable items | ||
On September | such as fuel assemblies, reactivity control assemblies, and nuclear instrumentation because | ||
30, 2005, the NRC issued NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," (ADAMS Accession | these components are not subject to an AMR, as defined in 10 CFR 54.21(a)(1). | ||
Nos. ML052770419 | On June 22, 2011, the NRC issued its final SE regarding topical report MRP-227, Revision 0 | ||
and ML052780376). | (ADAMS Accession No. ML 111600498), which license renewal applicants and renewed license | ||
On December 31, 2010, the NRC issued NUREG-1801, Revision 2, "Generic Aging Lessons Learned (GALL) Report," (ADAMS Accession | holders will use to develop their plant-specific AMPs for RVI components. This SE contains | ||
No. ML 103490041). | specific conditions on the use of the topical report and applicant/licensee action items that must | ||
The GALL Report provides generic AMRs of systems, structures, and components | be addressed by those utilizing the topical report as the basis for a submittal to the NRC. The | ||
that are within the scope of license renewal, as described | NRC approved version of the topical report is designated as MRP-227-A. | ||
in 10 CFR 54.4, and provides generic AMPs that the staff has found acceptable | Subsequent to the submittal of MRP-227 and prior to the issuance of theSE on MRP-227, | ||
to manage the effects of aging identified | GALL Report, Revision 2 was issued, providing new AMR line items and aging management | ||
in the AMR. As described | OAGI0001161 00003 | ||
in NUREG-1800, Revision 2, "Standard | |||
Review Plan for Review of License Renewal Applications | RIS 2011-07 | ||
for Nuclear Power Plants" (ADAMS Accession | Page 4 of 7 | ||
No. ML 103490036) (LR-SRP), treatment | guidance in AMP XI.M16A, "PWR Vessel Internals." This AMP was based on staff expectations | ||
of the GALL Report as an approved topical report improves the efficiency | for the guidance to be provided in MRP-227-A. After December 21, 2010, any licensees | ||
of the license renewal process. An applicant | submitting an LRA were encouraged to reference and utilize GALL Report, Revision 2 to | ||
may reference | manage the effects of aging identified in the AMR. With the issuance of theSE for MRP-227, | ||
in its LRA that its AMPs are consistent | the NRC will issue License Renewal Interim Staff Guidance (LR-ISG) to revise the GALL Report | ||
with those in the GALL Report. If an applicant | AMR line items and AMP XI.M.16A for consistency with theSE and to reflect acceptability of the | ||
takes credit for | MRP-227-A report for use in license renewal applications. | ||
an AMP in the GALL Report, it is incumbent | SUMMARY OF ISSUE | ||
on the applicant | The NRC granted renewed licenses to some owners of PWR units based on a commitment in | ||
to ensure that the conditions | the FSAR supplement to, in part, submit an inspection plan for RVI components to the NRC for | ||
and operating | review and approval. This plan was to be based on aging management guidelines for RVI | ||
experience | components developed by the industry and approved by the NRC. This commitment in the | ||
at the plant are bounded by those for which the AMP in the GALL Report was evaluated | FSAR would require those licensees to review and update their aging management inspection | ||
and found acceptable. | plans for RVI components based on the guidance provided in MRP-227-A. | ||
In such a case, the NRC staff's review of the AMP is limited to verifying | With the issuance of the staff SE for MRP-227, the NRC has updated internal guidance on | ||
that the applicant's | implementation of this RVI component AMP guidance relative to license renewal for PWR plants | ||
AMP is consistent | on a plant-specific basis, as indicated in the following table for the plants in Categories "A" | ||
with that provided in the GALL Report, including | through "D." The different plant categories reflect the licensee's status relative to license | ||
the conditions | renewal approval (i.e., licensee has received a renewed license, has submitted an LRA, or has | ||
and operating | not), and, for those plants with renewed licenses, whether the licensee has or has not submitted | ||
experience | its inspection plan to the NRC for review and approval. | ||
provided in the GALL Report. If the applicant's | Category "A" facilities address licensees that previously submitted an RVI inspection plan based | ||
conditions | on the draft Revision 0 of MRP-227. Licensees of Category "A" facilities, those that made a | ||
and operating | commitment in the FSAR supplement to comply with the industry-developed guidance and | ||
experience | choose to withdraw their inspection plans to conform to their commitments, must do so in writing | ||
are not bounded by those of the GALL Report AMP, it is incumbent | and should include a commitment to resubmit the required information based on MRP-227-A, no | ||
on the applicant | later than October 1, 2012. Licensees of Category "A" facilities who propose in their resubmittal | ||
to address the additional | to deviate from provisions of MRP-227-A based upon having completed specific inspections, will | ||
effects of aging that may apply to the applicant's | need to provide a justification for each deviation from the MRP-227-A guidelines. The NRC will | ||
facility and supplement | evaluate proposed deviations from the MRP-227-A guidelines to ensure that licensee programs | ||
the GALL Report AMR line items and AMPs as necessary. | will still provide an acceptable approach for managing the effects of aging in RVI components. | ||
The staff's review then addresses | This will ensure compliance with the commitment in the FSAR supplement. | ||
the acceptability | Licensees of Category "B" facilities that have committed to follow the industry-developed | ||
of the AMR and the AMPs to be used by the applicant. | guidance, will be expected to make the submittal of their RVI AMP based on the guidance of | ||
Revision 1 of the GALL Report provides AMP XI.M16, "PWR Vessel Internals," which refers to the aging management | MRP-227-A, consistent with their commitment. Licensees of Category "B" facilities who are | ||
guidance of the AMR line items for RVI components. | required by their commitments to submit their RVI inspection plan prior to one year after the | ||
Within the context OAGI0001161 | issuance of this RIS may modify their commitments to submit their RVI inspection plan no later | ||
than October 1, 2012. All other Category "B" facility licensees will be expected to make the | |||
RIS 2011-07 Page 3 of 7 of this RIS, NRC license renewals, theSE for MRP-227 and other NRC licensing | submittal of their RVI AMP in accordance with their existing commitments. This will ensure | ||
actions, "RVI" refers to reactor vessel internals. | compliance with the commitment in the FSAR supplement. | ||
In recognition | OAGI0001161 00004 | ||
that the industry was conducting | |||
programs to investigate | RIS 2011-07 | ||
aging of RVI components | Page 5 of 7 | ||
and to develop aging management | For those PWR plants that have an LRA currently under review (as addressed in Category "C") | ||
guidelines | with a commitment to follow the industry-developed guidance, the NRC staff expects the | ||
for RVI components, the AMR line items for RVI components | applicant to revise the commitment for aging management of PWR vessel internals such that | ||
state that: No further aging management | the plant-specific action items identified in theSE for MRP-227 would be submitted to the NRC | ||
review is necessary | for review and approval not later than two years after issuance of the renewed license and not | ||
if the applicant | later than two years before the plant enters the period of extended operation, whichever comes | ||
provides a commitment | first. It is expected that Category C licensees will follow the guidance of MRP-227-A, consistent | ||
in the FSAR [final safety analysis report] supplement | with their commitment. | ||
to (1) participate | For those PWR plant licensees that have not submitted their LRAs (as addressed in Category | ||
in the industry programs for investigating | "D") but plan to submit an LRA in the future, the NRC staff encourages these future license | ||
and managing aging effects on reactor internals; | renewal applicants to, and anticipates that the applicant will, provide an AMP for vessel internals | ||
(2) evaluate and implement | in their LRA that is consistent with MRP-227-A. As described previously, the NRC will issue an | ||
the results of the industry programs as applicable | LR-ISG to revise the GALL Report to ensure that GALL AMP XI.M16A, "PWR Vessel Internals," | ||
to the reactor internals; | and associated AMR line items are consistent with theSE on MRP-227 and reflect acceptability | ||
and (3) upon completion | of the MRP-227-A report for use in license renewal applications. It is expected that all | ||
of these programs, but not less than 24 months before entering the period of extended operation, submit an inspection | Category D LRAs will meet GALL Revision 2 as updated by the LR-ISG. | ||
plan for reactor internals | If a license renewal applicant confirms that it will implement an AMP consistent with | ||
to the NRC for review and approval. | MRP-227-A, Licensee/Applicant Action Item 8 from the NRC staff SE (Section 3.5.1) indicates | ||
Each licensee that made a commitment | that the LRA shall include, in part, an AMP that addresses the 10 program elements as defined | ||
to conform to GALL AMP XI.M16, or an equivalent | in AMP XI.M16A, and an inspection plan. The NRC review of an AMP which is consistent with | ||
commitment | GALL AMP XI.M16A would include those items specifically identified in Section 4.0 of theSE. | ||
under the 2001 GALL Report, also made a commitment | Category Description NRC Expectations | ||
in its FSAR supplement | Licensees may withdraw their current | ||
that it will implement | Plants with renewed licenses that AMP/inspection plan submittals and provide | ||
a plant-specific | have already submitted an new/revised commitments to resubmit | ||
AMP for its RVI components | A AMP/inspection plan based on AMPs/inspection plans in accordance with | ||
based on the developed | MRP-227, Revision 0 to comply MRP-227-A no later than October 1, 2012. | ||
guidance. | with an existing commitment. Future submittals should address all | ||
On January 12, 2009, the Electric Power Research Institute (EPRI) submitted | information required by MRP-227-A. | ||
for NRC staff review and approval the Materials | Licensees will be expected to submit | ||
Reliability | AMPs/inspection plans in accordance with | ||
Program (MRP) Report 1016596 (MRP-227), Revision 0, "Pressurized | MRP-227-A, consistent with the timing | ||
Water Reactor Internals | Plants with renewed licenses that | ||
Inspection | requirements reflected in their LR | ||
and Evaluation | have a commitment to submit an | ||
Guidelines" (ADAMS Accession | commitments. Licensees who would be | ||
No. ML090160204). | AMP/inspection plan based on | ||
MRP-227 is the industry-developed | B required by their commitments to make their | ||
guidance that licensees | MRP-227, but that have not yet | ||
will use to develop their plant-specific | submittal prior to one year after the issuance | ||
AMP for RVI components. | been required to do so by their | ||
MRP-227, Revision 0 contains a discussion | of this RIS may modify their commitments to | ||
of the technical | commitment. | ||
basis for the development | reflect a requirement to submit their | ||
of plant-specific | AMPs/inspection plans no later than | ||
AMPs for RVI components | October 1, 2012. | ||
in PWR vessels. MRP-227, Revision 0 also provides inspection | OAGI0001161 00005 | ||
guidelines | RIS 2011-07 | ||
for PWR licensees | Page 6 of 7 | ||
to use in their plant-specific | Applicants will be expected to revise their | ||
AMPs. Once approved by the NRC, MRP-227 will provide the basis for renewed license holders to develop plant-specific | commitment for aging management of PWR | ||
inspection | vessel internals such that the submittal | ||
plans to manage aging effects on RVI components, as described | information identified in the SE for MRP-227 | ||
by their FSAR commitment. | Plants that have an LRA currently would be submitted to the NRC for review | ||
The scope of components | c under review. and approval not later than two years after | ||
considered | issuance of the renewed license and not later | ||
for inspection | than two years before the plant enters the | ||
under the guidance of MRP-227, Revision 0 includes core support structures (typically | period of extended operation, whichever | ||
denoted as Examination | comes first. | ||
Category B-N-3 by Section XI of the American Society of Mechanical | Applicants will be expected to submit an AMP | ||
Engineers | Plants that will apply for an LR in | ||
Boiler and Pressure Vessel Code), and those RVI components | for vessel internals that is consistent with | ||
that serve an intended safety function consistent | D the future based on the GALL | ||
with the criteria in 10 CFR 54.4(a)(1). | MRP-227-A for NRC staff review and | ||
The scope of the program does not include consumable | Report, Revision 2. | ||
approval. | |||
control assemblies, and nuclear instrumentation | BACKFIT DISCUSSION | ||
This RIS is being issued to inform stakeholders of the implementation of updated internal NRC | |||
are not subject to an AMR, as defined in 10 CFR 54.21(a)(1). | guidance for staff in performing reviews of LRAs with AMPs. The backfit rule applies to | ||
On June 22, 2011, the NRC issued its final SE regarding | procedures necessary to operate a nuclear power plant. The NRC's regulatory review process | ||
topical report MRP-227, Revision 0 (ADAMS Accession | is not a licensee procedure required for operating the plant. | ||
No. ML 111600498), which license renewal applicants | This RIS requires no action or written response. The intent is to provide licensees sufficient | ||
and renewed license holders will use to develop their plant-specific | time to modify their AMPs to be consistent with MRP-227-A. This RIS provides information to | ||
AMPs for RVI components. | licensees regarding (1) updated NRC procedures for LRA reviews or the review of certain | ||
This SE contains specific conditions | licensee submittals related to commitments made in the process of receiving a renewed license | ||
on the use of the topical report and applicant/licensee | and (2) the potential for licensees to modify the original commitment date for the submittal of a | ||
action items that must be addressed | RVI AMP for their facilities. The technical position of GALL Rev. 2 has not changed. | ||
by those utilizing | Compliance with the guidelines specified in MRP-227-A would satisfy a licensee's license | ||
the topical report as the basis for a submittal | renewal commitment. For those applicants following GALL Rev. 1, which provided no definition | ||
to the NRC. The NRC approved version of the topical report is designated | on the RVI AMP, other than following the industry's future program, this RIS provides | ||
as MRP-227-A. | clarification as to what an acceptable RVI AMP would be in light of the issuance of the staff SE | ||
Subsequent | of MRP-227. Any action on the part of addressees to submit a request for a licensing action or | ||
to the submittal | to adhere to the industry guidance contained in the EPRI's MRP-227-A guidance document is | ||
of MRP-227 and prior to the issuance of theSE on MRP-227, GALL Report, Revision 2 was issued, providing | strictly voluntary. Any changes to a licensees' AMP/inspection plan to adhere to MRP 227-A, | ||
new AMR line items and aging management | ensures compliance with a license commitment. Therefore, this RIS does not constitute a | ||
OAGI0001161 | backfit under 10 CFR 50.109, "Backfitting," and a backfit analysis is not required. | ||
FEDERAL REGISTER NOTIFICATION | |||
RIS 2011-07 Page 4 of 7 guidance in AMP XI.M16A, "PWR Vessel Internals." This AMP was based on staff expectations | This RIS is informational and does not represent a departure from current regulatory | ||
for the guidance to be provided in MRP-227-A. | requirements. The NRC did not publish a notice of opportunity for public comment on this RIS | ||
After December 21, 2010, any licensees | in the Federal Register because the RIS pertains to an administrative aspect of the regulatory | ||
submitting | process that involves the voluntary use of industry guidance by addressees. However, on | ||
an LRA were encouraged | OAGI0001161 00006 | ||
to reference | |||
and utilize GALL Report, Revision 2 to manage the effects of aging identified | RIS 2011-07 | ||
in the AMR. With the issuance of theSE for MRP-227, the NRC will issue License Renewal Interim Staff Guidance (LR-ISG) to revise the GALL Report AMR line items and AMP XI.M.16A for consistency | Page 7 of 7 | ||
with theSE and to reflect acceptability | June 13, 2011, the NRC posted a draft version of this RIS on its public website for a 10-day | ||
of the MRP-227-A | public comment period. Comments were received from the industry's Materials Reliability | ||
report for use in license renewal applications. | Program (ADAMS Accession No. ML 11188A 162) and considered. | ||
SUMMARY OF ISSUE The NRC granted renewed licenses to some owners of PWR units based on a commitment | CONGRESSIONAL REVIEW ACT | ||
The NRC has determined that this action is not a rule as designated by the Congressional | |||
to, in part, submit an inspection | Review Act (5 U.S.C. §§ 801-808) and, therefore, is not subject to the Act. | ||
plan for RVI components | PAPERWORK REDUCTION ACT STATEMENT | ||
to the NRC for review and approval. | This RIS does not contain new or amended information collection requirements that are subject | ||
This plan was to be based on aging management | to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing requirements were | ||
guidelines | approved by the Office of Management and Budget (OMB), approval number 3150-0011 and | ||
for RVI components | 3150-0155. | ||
developed | PUBLIC PROTECTION NOTIFICATION | ||
by the industry and approved by the NRC. This commitment | The NRC may not conduct or sponsor, and a person is not required to respond to, a request for | ||
in the FSAR would require those licensees | information or an information collection requirement unless the requesting document displays a | ||
to review and update their aging management | currently valid OMB control number. | ||
inspection | CONTACT | ||
plans for RVI components | Please direct any questions about this matter to the technical contact listed below. | ||
based on the guidance provided in MRP-227-A. | IRA/ | ||
With the issuance of the staff SE for MRP-227, the NRC has updated internal guidance on implementation | Timothy J. McGinty, Director | ||
of this RVI component | Division of Policy and Rulemaking | ||
AMP guidance relative to license renewal for PWR plants on a plant-specific | Office of Nuclear Reactor Regulation | ||
basis, as indicated | Technical Contact: Sheldon D. Stuchell, Senior Project Manager | ||
in the following | NRR/DPR/PLPB | ||
table for the plants in Categories "A" through "D." The different | (301) 415-1487 | ||
plant categories | E-mail: sheldon.stuchell@nrc.gov | ||
reflect the licensee's | Note: NRC generic communications may be found on the NRC public Web site, | ||
status relative to license renewal approval (i.e., licensee has received a renewed license, has submitted | http://www.nrc.gov, under NRC Library/Document Collections. | ||
an LRA, or has not), and, for those plants with renewed licenses, whether the licensee has or has not submitted | OAGI0001161 00007 | ||
its inspection | |||
plan to the NRC for review and approval. | |||
Category "A" facilities | ML 11188A 162) and considered. | ||
address licensees | CONGRESSIONAL REVIEW ACT | ||
that previously | The NRC has determined that this action is not a rule as designated by the Congressional | ||
submitted | Review Act (5 U.S.C. §§ 801-808) and, therefore, is not subject to the Act. | ||
an RVI inspection | PAPERWORK REDUCTION ACT STATEMENT | ||
plan based on the draft Revision 0 of MRP-227. Licensees | This RIS does not contain new or amended information collection requirements that are subject | ||
of Category "A" facilities, those that made a commitment | to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing requirements were | ||
in the FSAR supplement | approved by the Office of Management and Budget (OMB), approval number 3150-0011 and | ||
to comply with the industry-developed | 3150-0155. | ||
guidance and choose to withdraw their inspection | PUBLIC PROTECTION NOTIFICATION | ||
plans to conform to their commitments, must do so in writing and should include a commitment | The NRC may not conduct or sponsor, and a person is not required to respond to, a request for | ||
to resubmit the required information | information or an information collection requirement unless the requesting document displays a | ||
based on MRP-227-A, no later than October 1, 2012. Licensees | currently valid OMB control number. | ||
of Category "A" facilities | CONTACT | ||
who propose in their resubmittal | Please direct any questions about this matter to the technical contact listed below. | ||
to deviate from provisions | IRA/ | ||
of MRP-227-A | Timothy J. McGinty, Director | ||
based upon having completed | Division of Policy and Rulemaking | ||
specific inspections, will need to provide a justification | Office of Nuclear Reactor Regulation | ||
for each deviation | Technical Contact: Sheldon D. Stuchell, Senior Project Manager | ||
from the MRP-227-A | NRR/DPR/PLPB | ||
guidelines. | (301) 415-1487 | ||
The NRC will evaluate proposed deviations | E-mail: sheldon.stuchell@nrc.gov | ||
from the MRP-227-A | Note: NRC generic communications may be found on the NRC public Web site, | ||
guidelines | http://www.nrc.gov, under NRC Library/Document Collections. | ||
to ensure that licensee programs will still provide an acceptable | DISTRIBUTION: MMitchell, NRR MEvans, NRR BHolian, NRR AHiser, NRR | ||
approach for managing the effects of aging in RVI components. | ADAMS Accession Number: ML 111990086 *via e-mail TAC ME5988 | ||
This will ensure compliance | OFFICE NRR/DPR/PLPB/PM Tech Editor NRR/DCI/CVIB/BC NRR/DPR/PLPB/BC NRR/PMDA | ||
with the commitment | NAME SStuchell* JDougherty* MMitchell* JJolicoeur LHill* | ||
in the FSAR supplement. | DATE 05/18/11 04/08/11 04/22/11 04/22/11 04/25/11 | ||
Licensees | OFFICE OE OIS NRR/DORL/D NRR/DCI/D NRR/DLR/D | ||
of Category "B" facilities | MEvans (JLubinski | ||
that have committed | NAME NHilton* TDonnell* JGiitter* BHolian* | ||
to follow the industry-developed | for) | ||
guidance, will be expected to make the submittal | DATE 05/16/11 04/28/11 05/16/11 05/04/11 04/29/11 | ||
of their RVI AMP based on the guidance of MRP-227-A, consistent | NRR/DPR/PGCB/ | ||
with their commitment. | OFFICE OGC NRR/DPR/PGCB/PM NRR/DPR/PGCB/BC NRR/DPR/D | ||
Licensees | LA | ||
of Category "B" facilities | NAME MSmith* (NLO) CHawes ARussell SRosenberg TMcGinty | ||
who are required by their commitments | DATE 06/02/11 07/18/11 07/18/11 07/19/11 07/21/11 | ||
to submit their RVI inspection | |||
plan prior to one year after the issuance of this RIS may modify their commitments | |||
to submit their RVI inspection | |||
plan no later than October 1, 2012. All other Category "B" facility licensees | |||
will be expected to make the submittal | |||
of their RVI AMP in accordance | |||
with their existing commitments. | |||
This will ensure compliance | |||
with the commitment | |||
in the FSAR supplement. | |||
OAGI0001161 | |||
RIS 2011-07 Page 5 of 7 For those PWR plants that have an LRA currently | |||
under review (as addressed | |||
in Category "C") with a commitment | |||
to follow the industry-developed | |||
guidance, the NRC staff expects the applicant | |||
to revise the commitment | |||
for aging management | |||
of PWR vessel internals | |||
such that the plant-specific | |||
action items identified | |||
in theSE for MRP-227 would be submitted | |||
to the NRC for review and approval not later than two years after issuance of the renewed license and not later than two years before the plant enters the period of extended operation, whichever | |||
will follow the guidance of MRP-227-A, consistent | |||
with their commitment. | |||
For those PWR plant licensees | |||
that have not submitted | |||
their LRAs (as addressed | |||
in Category "D") but plan to submit an LRA in the future, the NRC staff encourages | |||
these future license renewal applicants | |||
to, and anticipates | |||
that the applicant | |||
will, provide an AMP for vessel internals | |||
in their LRA that is consistent | |||
with MRP-227-A. | |||
As described | |||
previously, the NRC will issue an LR-ISG to revise the GALL Report to ensure that GALL AMP XI.M16A, "PWR Vessel Internals," and associated | |||
AMR line items are consistent | |||
with theSE on MRP-227 and reflect acceptability | |||
of the MRP-227-A | |||
report for use in license renewal applications. | |||
It is expected that all Category D LRAs will meet GALL Revision 2 as updated by the LR-ISG. If a license renewal applicant | |||
confirms that it will implement | |||
an AMP consistent | |||
Action Item 8 from the NRC staff SE (Section 3.5.1) indicates | |||
that the LRA shall include, in part, an AMP that addresses | |||
the 10 program elements as defined in AMP XI.M16A, and an inspection | |||
plan. The NRC review of an AMP which is consistent | |||
identified | |||
in Section 4.0 of theSE. Category Description | |||
NRC Expectations | |||
Licensees | |||
may withdraw their current Plants with renewed licenses that AMP/inspection | |||
plan submittals | |||
and provide have already submitted | |||
an new/revised | |||
commitments | |||
to resubmit A AMP/inspection | |||
plan based on AMPs/inspection | |||
plans in accordance | |||
no later than October 1, 2012. with an existing commitment. | |||
Future submittals | |||
should address all information | |||
required by MRP-227-A. | |||
Licensees | |||
will be expected to submit AMPs/inspection | |||
plans in accordance | |||
with the timing have a commitment | |||
to submit an | |||
plan based on | |||
to | |||
reflect a requirement | |||
to submit their AMPs/inspection | |||
plans no later than October 1, 2012. OAGI0001161 | |||
00005 | |||
RIS 2011-07 Page 6 of 7 Applicants | |||
will be expected to revise their commitment | |||
for aging management | |||
of PWR vessel internals | |||
such that the submittal | |||
information | |||
identified | |||
in the SE for MRP-227 would be submitted | |||
to the NRC for review and approval not later than two years after issuance of the renewed license and not later than two years before the plant enters the period of extended operation, whichever | |||
comes first. Applicants | |||
will be expected to submit an AMP for vessel internals | |||
that is consistent | |||
for NRC staff review and approval. | |||
This RIS is being issued to inform stakeholders | |||
of the implementation | |||
of updated internal NRC guidance for staff in performing | |||
reviews of LRAs with AMPs. The backfit rule applies to procedures | |||
necessary | |||
to operate a nuclear power plant. The NRC's regulatory | |||
review process is not a licensee procedure | |||
required for operating | |||
the plant. This RIS requires no action or written response. | |||
The intent is to provide licensees | |||
sufficient | |||
time to modify their AMPs to be consistent | |||
with MRP-227-A. | |||
This RIS provides information | |||
regarding | |||
(1) updated NRC procedures | |||
for LRA reviews or the review of certain licensee submittals | |||
related to commitments | |||
made in the process of receiving | |||
a renewed license and (2) the potential | |||
for licensees | |||
to modify the original commitment | |||
date for the submittal | |||
of a RVI AMP for their facilities. | |||
The technical | |||
position of GALL Rev. 2 has not changed. Compliance | |||
with the guidelines | |||
specified | |||
in MRP-227-A | |||
would satisfy a licensee's | |||
For those applicants | |||
following | |||
GALL Rev. 1, which provided no definition | |||
on the RVI AMP, other than following | |||
the industry's | |||
future program, this RIS provides clarification | |||
as to what an acceptable | |||
RVI AMP would be in light of the issuance of the staff SE of MRP-227. Any action on the part of addressees | |||
to submit a request for a licensing | |||
action or to adhere to the industry guidance contained | |||
in the EPRI's MRP-227-A | |||
guidance document is strictly voluntary. | |||
Any changes to a licensees' | |||
AMP/inspection | |||
plan to adhere to MRP 227-A, ensures compliance | |||
with a license commitment. | |||
Therefore, this RIS does not constitute | |||
FEDERAL REGISTER NOTIFICATION | |||
This RIS is informational | |||
and does not represent | |||
a departure | |||
from current regulatory | |||
requirements. | |||
The NRC did not publish a notice of opportunity | |||
for public comment on this RIS in the Federal Register because the RIS pertains to an administrative | |||
aspect of the regulatory | |||
process that involves the voluntary | |||
use of industry guidance by addressees. | |||
However, on OAGI0001161 | |||
RIS 2011-07 Page 7 of 7 June 13, 2011, the NRC posted a draft version of this RIS on its public website for a | |||
Materials | |||
Reliability | |||
Program (ADAMS Accession | |||
No. ML 11188A 162) and considered. | |||
CONGRESSIONAL | |||
REVIEW ACT The NRC has determined | |||
that this action is not a rule as designated | |||
by the Congressional | |||
Review Act (5 U.S.C. §§ 801-808) and, therefore, is not subject to the Act. PAPERWORK | |||
REDUCTION | |||
ACT STATEMENT | |||
This RIS does not contain new or amended information | |||
collection | |||
requirements | |||
that are subject to the Paperwork | |||
Reduction | |||
Act of 1995 (44 U.S.C. 3501 et seq.). Existing requirements | |||
and Budget (OMB), approval number 3150-0011 | |||
PUBLIC PROTECTION | |||
NOTIFICATION | |||
The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information | |||
or an information | |||
collection | |||
requirement | |||
unless the requesting | |||
document displays a currently | |||
valid OMB control number. CONTACT Please direct any questions | |||
about this matter to the technical | |||
contact listed below. IRA/ Timothy J. McGinty, Director Division of Policy and Rulemaking | |||
Office of Nuclear Reactor Regulation | |||
Technical | |||
Contact: Sheldon D. Stuchell, Senior Project Manager NRR/DPR/PLPB | |||
(301) 415-1487 E-mail: sheldon.stuchell@nrc.gov | |||
Note: NRC generic communications | |||
may be found on the NRC public Web site, http://www.nrc.gov, under NRC Library/Document | |||
Collections. | |||
OAGI0001161 | |||
that | |||
collection | |||
BHolian | |||
NRR/DPR/ | |||
NRR/ | |||
NAME | |||
}} | }} |
Latest revision as of 11:25, 12 November 2019
ML11356A317 | |
Person / Time | |
---|---|
Site: | Indian Point |
Issue date: | 07/21/2011 |
From: | Mcginty T Office of Nuclear Reactor Regulation |
To: | Atomic Safety and Licensing Board Panel |
SECY RAS | |
Shared Package | |
ML11356A300 | List: |
References | |
RAS 21618, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 RIS-11-007 | |
Download: ML11356A317 (8) | |
See also: RIS 2011-07
Text
NYS000310
Submitted: December 22, 2011
UNITED STATES
NUCLEAR REGULA TORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, DC 20555-0001
July 21, 2011
NRC REGULATORY ISSUE SUMMARY 2011-07
LICENSE RENEWAL SUBMITTAL INFORMATION FOR
PRESSURIZED WATER REACTOR INTERNALS AGING MANAGEMENT
ADDRESSEES
All holders of and applicants for a pressurized water power reactor operating license or
construction permit under Title 10 of the Code of Federal Regulations (10 CFR) Part 50,
"Domestic Licensing of Production and Utilization Facilities," except those that have
permanently ceased operations and have certified that fuel has been permanently removed
from the reactor vessel.
INTENT
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)
to inform addressees of updated NRC procedures for license renewal application (LRA) reviews
or the review of certain licensee submittals related to commitments made in the process of
receiving a renewed license. LRAs for pressurized water reactor (PWR) plants have identified
that an aging management program (AMP) is needed to manage the effects of aging for reactor
vessel internal (RVI) components that are within the scope of license renewal, in accordance
with 10 CFR Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power
Plants." This RIS requires no action or written response on the part of addressees. This RIS
also provides information to licensees with respect to how to meet their existing license renewal
commitments related to reactor vessel internals aging management programs, and on
acceptable changes to existing license renewal commitments in order to account for the recent
issue of the staff's final Safety Evaluation (SE) of MRP-227, Rev.O, and the forthcoming issue of
the approved version of MRP-227.
The purpose of this RIS is to facilitate a predictable and consistent method for reviewing the
AMPs of commercial PWR LRAs and the AMPs and inspection plans for PWR plants that have
received renewed operating licenses. This RIS does not transmit or imply any new or changed
requirements or staff positions. Although no specific action or written response is required, the
information contained in this RIS will enable licensees to plan effectively for anticipated LRAs
and inspection activities.
This RIS is part of the NRC's ongoing oversight of license renewal and is unrelated to the
agency's response to the March 11, 2011, earthquake in Japan.
OAGI0001161 00001
Page 2 of 7
BACKGROUND INFORMATION
In 10 CFR Part 54, the NRC addresses the requirements for plant LRAs. The regulation in
10 CFR 54.21, "Contents of Application-Technical Information," requires that each LRA
contain an integrated plant assessment and an evaluation of time-limited aging analyses. The
integrated plant assessment must identify and list those structures and components subject to
an aging management review (AMR) and must demonstrate that the effects of aging (such as
cracking, loss of material, loss of fracture toughness, dimensional changes, and loss of preload)
will be adequately managed so that the intended functions of the structures and components will
be maintained consistent with the current licensing basis for the period of extended operation as
required by 10 CFR 54.29(a). Structures and components subject to an AMR shall encompass
those structures and components (1) that perform an intended function, as described in
10 CFR 54.4, "Scope," without moving parts or without a change in configuration or properties,
and (2) that are not subject to replacement based on a qualified life or specified time period.
These structures and components are referred to as "passive" and "long-lived," respectively.
On April 26, 2001, the NRC issued N UREG-1801, "Generic Aging Lessons Learned (GALL)
Report," (Agencywide Documents Access and Management System (ADAMS) Accession Nos.
ML011080185 and ML011080393). On September 30, 2005, the NRC issued NUREG-1801,
Revision 1, "Generic Aging Lessons Learned (GALL) Report," (ADAMS Accession Nos.
ML052770419 and ML052780376). On December 31, 2010, the NRC issued NUREG-1801,
Revision 2, "Generic Aging Lessons Learned (GALL) Report," (ADAMS Accession No.
ML 103490041). The GALL Report provides generic AMRs of systems, structures, and
components that are within the scope of license renewal, as described in 10 CFR 54.4, and
provides generic AMPs that the staff has found acceptable to manage the effects of aging
identified in the AMR. As described in NUREG-1800, Revision 2, "Standard Review Plan for
Review of License Renewal Applications for Nuclear Power Plants" (ADAMS Accession No.
ML 103490036) (LR-SRP), treatment of the GALL Report as an approved topical report
improves the efficiency of the license renewal process.
An applicant may reference in its LRA that its AMPs are consistent with those in the GALL
Report. If an applicant takes credit for an AMP in the GALL Report, it is incumbent on the
applicant to ensure that the conditions and operating experience at the plant are bounded by
those for which the AMP in the GALL Report was evaluated and found acceptable. In such a
case, the NRC staff's review of the AMP is limited to verifying that the applicant's AMP is
consistent with that provided in the GALL Report, including the conditions and operating
experience provided in the GALL Report.
If the applicant's conditions and operating experience are not bounded by those of the GALL
Report AMP, it is incumbent on the applicant to address the additional effects of aging that may
apply to the applicant's facility and supplement the GALL Report AMR line items and AMPs as
necessary. The staff's review then addresses the acceptability of the AMR and the AMPs to be
used by the applicant.
Revision 1 of the GALL Report provides AMP XI.M16, "PWR Vessel Internals," which refers to
the aging management guidance of the AMR line items for RVI components. Within the context
OAGI0001161 00002
Page 3 of 7
of this RIS, NRC license renewals, theSE for MRP-227 and other NRC licensing actions, "RVI"
refers to reactor vessel internals. In recognition that the industry was conducting programs to
investigate aging of RVI components and to develop aging management guidelines for RVI
components, the AMR line items for RVI components state that:
No further aging management review is necessary if the applicant provides a
commitment in the FSAR [final safety analysis report] supplement to (1) participate in the
industry programs for investigating and managing aging effects on reactor internals; (2)
evaluate and implement the results of the industry programs as applicable to the reactor
internals; and (3) upon completion of these programs, but not less than 24 months
before entering the period of extended operation, submit an inspection plan for reactor
internals to the NRC for review and approval.
Each licensee that made a commitment to conform to GALL AMP XI.M16, or an equivalent
commitment under the 2001 GALL Report, also made a commitment in its FSAR supplement
that it will implement a plant-specific AMP for its RVI components based on the industry-
developed guidance.
On January 12, 2009, the Electric Power Research Institute (EPRI) submitted for NRC staff
review and approval the Materials Reliability Program (MRP) Report 1016596 (MRP-227),
Revision 0, "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines"
(ADAMS Accession No. ML090160204). MRP-227 is the industry-developed guidance that
licensees will use to develop their plant-specific AMP for RVI components. MRP-227,
Revision 0 contains a discussion of the technical basis for the development of plant-specific
AMPs for RVI components in PWR vessels. MRP-227, Revision 0 also provides inspection and
evaluation guidelines for PWR licensees to use in their plant-specific AMPs. Once approved by
the NRC, MRP-227 will provide the basis for renewed license holders to develop plant-specific
inspection plans to manage aging effects on RVI components, as described by their FSAR
commitment.
The scope of components considered for inspection under the guidance of MRP-227,
Revision 0 includes core support structures (typically denoted as Examination Category B-N-3
by Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel
Code), and those RVI components that serve an intended safety function consistent with the
criteria in 10 CFR 54.4(a)(1). The scope of the program does not include consumable items
such as fuel assemblies, reactivity control assemblies, and nuclear instrumentation because
these components are not subject to an AMR, as defined in 10 CFR 54.21(a)(1).
On June 22, 2011, the NRC issued its final SE regarding topical report MRP-227, Revision 0
(ADAMS Accession No. ML 111600498), which license renewal applicants and renewed license
holders will use to develop their plant-specific AMPs for RVI components. This SE contains
specific conditions on the use of the topical report and applicant/licensee action items that must
be addressed by those utilizing the topical report as the basis for a submittal to the NRC. The
NRC approved version of the topical report is designated as MRP-227-A.
Subsequent to the submittal of MRP-227 and prior to the issuance of theSE on MRP-227,
GALL Report, Revision 2 was issued, providing new AMR line items and aging management
OAGI0001161 00003
Page 4 of 7
guidance in AMP XI.M16A, "PWR Vessel Internals." This AMP was based on staff expectations
for the guidance to be provided in MRP-227-A. After December 21, 2010, any licensees
submitting an LRA were encouraged to reference and utilize GALL Report, Revision 2 to
manage the effects of aging identified in the AMR. With the issuance of theSE for MRP-227,
the NRC will issue License Renewal Interim Staff Guidance (LR-ISG) to revise the GALL Report
AMR line items and AMP XI.M.16A for consistency with theSE and to reflect acceptability of the
MRP-227-A report for use in license renewal applications.
SUMMARY OF ISSUE
The NRC granted renewed licenses to some owners of PWR units based on a commitment in
the FSAR supplement to, in part, submit an inspection plan for RVI components to the NRC for
review and approval. This plan was to be based on aging management guidelines for RVI
components developed by the industry and approved by the NRC. This commitment in the
FSAR would require those licensees to review and update their aging management inspection
plans for RVI components based on the guidance provided in MRP-227-A.
With the issuance of the staff SE for MRP-227, the NRC has updated internal guidance on
implementation of this RVI component AMP guidance relative to license renewal for PWR plants
on a plant-specific basis, as indicated in the following table for the plants in Categories "A"
through "D." The different plant categories reflect the licensee's status relative to license
renewal approval (i.e., licensee has received a renewed license, has submitted an LRA, or has
not), and, for those plants with renewed licenses, whether the licensee has or has not submitted
its inspection plan to the NRC for review and approval.
Category "A" facilities address licensees that previously submitted an RVI inspection plan based
on the draft Revision 0 of MRP-227. Licensees of Category "A" facilities, those that made a
commitment in the FSAR supplement to comply with the industry-developed guidance and
choose to withdraw their inspection plans to conform to their commitments, must do so in writing
and should include a commitment to resubmit the required information based on MRP-227-A, no
later than October 1, 2012. Licensees of Category "A" facilities who propose in their resubmittal
to deviate from provisions of MRP-227-A based upon having completed specific inspections, will
need to provide a justification for each deviation from the MRP-227-A guidelines. The NRC will
evaluate proposed deviations from the MRP-227-A guidelines to ensure that licensee programs
will still provide an acceptable approach for managing the effects of aging in RVI components.
This will ensure compliance with the commitment in the FSAR supplement.
Licensees of Category "B" facilities that have committed to follow the industry-developed
guidance, will be expected to make the submittal of their RVI AMP based on the guidance of
MRP-227-A, consistent with their commitment. Licensees of Category "B" facilities who are
required by their commitments to submit their RVI inspection plan prior to one year after the
issuance of this RIS may modify their commitments to submit their RVI inspection plan no later
than October 1, 2012. All other Category "B" facility licensees will be expected to make the
submittal of their RVI AMP in accordance with their existing commitments. This will ensure
compliance with the commitment in the FSAR supplement.
OAGI0001161 00004
Page 5 of 7
For those PWR plants that have an LRA currently under review (as addressed in Category "C")
with a commitment to follow the industry-developed guidance, the NRC staff expects the
applicant to revise the commitment for aging management of PWR vessel internals such that
the plant-specific action items identified in theSE for MRP-227 would be submitted to the NRC
for review and approval not later than two years after issuance of the renewed license and not
later than two years before the plant enters the period of extended operation, whichever comes
first. It is expected that Category C licensees will follow the guidance of MRP-227-A, consistent
with their commitment.
For those PWR plant licensees that have not submitted their LRAs (as addressed in Category
"D") but plan to submit an LRA in the future, the NRC staff encourages these future license
renewal applicants to, and anticipates that the applicant will, provide an AMP for vessel internals
in their LRA that is consistent with MRP-227-A. As described previously, the NRC will issue an
LR-ISG to revise the GALL Report to ensure that GALL AMP XI.M16A, "PWR Vessel Internals,"
and associated AMR line items are consistent with theSE on MRP-227 and reflect acceptability
of the MRP-227-A report for use in license renewal applications. It is expected that all
Category D LRAs will meet GALL Revision 2 as updated by the LR-ISG.
If a license renewal applicant confirms that it will implement an AMP consistent with
MRP-227-A, Licensee/Applicant Action Item 8 from the NRC staff SE (Section 3.5.1) indicates
that the LRA shall include, in part, an AMP that addresses the 10 program elements as defined
in AMP XI.M16A, and an inspection plan. The NRC review of an AMP which is consistent with
GALL AMP XI.M16A would include those items specifically identified in Section 4.0 of theSE.
Category Description NRC Expectations
Licensees may withdraw their current
Plants with renewed licenses that AMP/inspection plan submittals and provide
have already submitted an new/revised commitments to resubmit
A AMP/inspection plan based on AMPs/inspection plans in accordance with
MRP-227, Revision 0 to comply MRP-227-A no later than October 1, 2012.
with an existing commitment. Future submittals should address all
information required by MRP-227-A.
Licensees will be expected to submit
AMPs/inspection plans in accordance with
MRP-227-A, consistent with the timing
Plants with renewed licenses that
requirements reflected in their LR
have a commitment to submit an
commitments. Licensees who would be
AMP/inspection plan based on
B required by their commitments to make their
MRP-227, but that have not yet
submittal prior to one year after the issuance
been required to do so by their
of this RIS may modify their commitments to
commitment.
reflect a requirement to submit their
AMPs/inspection plans no later than
October 1, 2012.
OAGI0001161 00005
Page 6 of 7
Applicants will be expected to revise their
commitment for aging management of PWR
vessel internals such that the submittal
information identified in the SE for MRP-227
Plants that have an LRA currently would be submitted to the NRC for review
c under review. and approval not later than two years after
issuance of the renewed license and not later
than two years before the plant enters the
period of extended operation, whichever
comes first.
Applicants will be expected to submit an AMP
Plants that will apply for an LR in
for vessel internals that is consistent with
D the future based on the GALL
MRP-227-A for NRC staff review and
Report, Revision 2.
approval.
BACKFIT DISCUSSION
This RIS is being issued to inform stakeholders of the implementation of updated internal NRC
guidance for staff in performing reviews of LRAs with AMPs. The backfit rule applies to
procedures necessary to operate a nuclear power plant. The NRC's regulatory review process
is not a licensee procedure required for operating the plant.
This RIS requires no action or written response. The intent is to provide licensees sufficient
time to modify their AMPs to be consistent with MRP-227-A. This RIS provides information to
licensees regarding (1) updated NRC procedures for LRA reviews or the review of certain
licensee submittals related to commitments made in the process of receiving a renewed license
and (2) the potential for licensees to modify the original commitment date for the submittal of a
RVI AMP for their facilities. The technical position of GALL Rev. 2 has not changed.
Compliance with the guidelines specified in MRP-227-A would satisfy a licensee's license
renewal commitment. For those applicants following GALL Rev. 1, which provided no definition
on the RVI AMP, other than following the industry's future program, this RIS provides
clarification as to what an acceptable RVI AMP would be in light of the issuance of the staff SE
of MRP-227. Any action on the part of addressees to submit a request for a licensing action or
to adhere to the industry guidance contained in the EPRI's MRP-227-A guidance document is
strictly voluntary. Any changes to a licensees' AMP/inspection plan to adhere to MRP 227-A,
ensures compliance with a license commitment. Therefore, this RIS does not constitute a
backfit under 10 CFR 50.109, "Backfitting," and a backfit analysis is not required.
FEDERAL REGISTER NOTIFICATION
This RIS is informational and does not represent a departure from current regulatory
requirements. The NRC did not publish a notice of opportunity for public comment on this RIS
in the Federal Register because the RIS pertains to an administrative aspect of the regulatory
process that involves the voluntary use of industry guidance by addressees. However, on
OAGI0001161 00006
Page 7 of 7
June 13, 2011, the NRC posted a draft version of this RIS on its public website for a 10-day
public comment period. Comments were received from the industry's Materials Reliability
Program (ADAMS Accession No. ML 11188A 162) and considered.
CONGRESSIONAL REVIEW ACT
The NRC has determined that this action is not a rule as designated by the Congressional
Review Act (5 U.S.C. §§ 801-808) and, therefore, is not subject to the Act.
PAPERWORK REDUCTION ACT STATEMENT
This RIS does not contain new or amended information collection requirements that are subject
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing requirements were
approved by the Office of Management and Budget (OMB), approval number 3150-0011 and
3150-0155.
PUBLIC PROTECTION NOTIFICATION
The NRC may not conduct or sponsor, and a person is not required to respond to, a request for
information or an information collection requirement unless the requesting document displays a
currently valid OMB control number.
CONTACT
Please direct any questions about this matter to the technical contact listed below.
IRA/
Timothy J. McGinty, Director
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Technical Contact: Sheldon D. Stuchell, Senior Project Manager
NRR/DPR/PLPB
(301) 415-1487
E-mail: sheldon.stuchell@nrc.gov
Note: NRC generic communications may be found on the NRC public Web site,
http://www.nrc.gov, under NRC Library/Document Collections.
OAGI0001161 00007
ML 11188A 162) and considered.
CONGRESSIONAL REVIEW ACT
The NRC has determined that this action is not a rule as designated by the Congressional
Review Act (5 U.S.C. §§ 801-808) and, therefore, is not subject to the Act.
PAPERWORK REDUCTION ACT STATEMENT
This RIS does not contain new or amended information collection requirements that are subject
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing requirements were
approved by the Office of Management and Budget (OMB), approval number 3150-0011 and
3150-0155.
PUBLIC PROTECTION NOTIFICATION
The NRC may not conduct or sponsor, and a person is not required to respond to, a request for
information or an information collection requirement unless the requesting document displays a
currently valid OMB control number.
CONTACT
Please direct any questions about this matter to the technical contact listed below.
IRA/
Timothy J. McGinty, Director
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Technical Contact: Sheldon D. Stuchell, Senior Project Manager
NRR/DPR/PLPB
(301) 415-1487
E-mail: sheldon.stuchell@nrc.gov
Note: NRC generic communications may be found on the NRC public Web site,
http://www.nrc.gov, under NRC Library/Document Collections.
DISTRIBUTION: MMitchell, NRR MEvans, NRR BHolian, NRR AHiser, NRR
ADAMS Accession Number: ML 111990086 *via e-mail TAC ME5988
OFFICE NRR/DPR/PLPB/PM Tech Editor NRR/DCI/CVIB/BC NRR/DPR/PLPB/BC NRR/PMDA
NAME SStuchell* JDougherty* MMitchell* JJolicoeur LHill*
DATE 05/18/11 04/08/11 04/22/11 04/22/11 04/25/11
OFFICE OE OIS NRR/DORL/D NRR/DCI/D NRR/DLR/D
MEvans (JLubinski
NAME NHilton* TDonnell* JGiitter* BHolian*
for)
DATE 05/16/11 04/28/11 05/16/11 05/04/11 04/29/11
NRR/DPR/PGCB/
OFFICE OGC NRR/DPR/PGCB/PM NRR/DPR/PGCB/BC NRR/DPR/D
LA
NAME MSmith* (NLO) CHawes ARussell SRosenberg TMcGinty
DATE 06/02/11 07/18/11 07/18/11 07/19/11 07/21/11