RIS 2008-28, Endorsement of Nuclear Energy Institute Guidance for Reactor Vessel Head Heavy Load Lifts: Difference between revisions

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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001 December 1, 2008  
{{#Wiki_filter:UNITED STATES
 
                              NUCLEAR REGULATORY COMMISSION
NRC REGULATORY ISSUE SUMMARY 2008-28 ENDORSEMENT OF NUCLEAR ENERGY INSTITUTE GUIDANCE FOR REACTOR VESSEL HEAD HEAVY LOAD LIFTS  
                          OFFICE OF NUCLEAR REACTOR REGULATION
                                  WASHINGTON, D.C. 20555-0001 December 1, 2008 NRC REGULATORY ISSUE SUMMARY 2008-28 ENDORSEMENT OF NUCLEAR ENERGY INSTITUTE GUIDANCE
                FOR REACTOR VESSEL HEAD HEAVY LOAD LIFTS


==ADDRESSEES==
==ADDRESSEES==
Line 22: Line 24:


==INTENT==
==INTENT==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) to notify industry of methods approved by the NRC staff for evaluating changes to a facility's licensing basis related to reactor vessel head and other heavy load lifts. By letter dated September 5, 2008 (Agencywide Documents Access and Management System (ADAMS)  
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)
Accession No. ML082410532), the NRC staff transmitted its safety evaluation of the guidelines developed by the Nuclear Energy Institute (NEI) and contained in NEI 08-05, "Industry Initiative on Control of Heavy Loads," Revision 0 (ADAMS Accession No. ML082180684). With NRC staff clarifications and conditions noted in the safety evaluation, licensees may use these guidelines to voluntarily establish a revised licensing basis for handling of reactor vessel heads and other heavy loads that is consistent with the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59, "Changes, Tests and Experiments."  This RIS requires no action or written response by addressees.
to notify industry of methods approved by the NRC staff for evaluating changes to a facilitys licensing basis related to reactor vessel head and other heavy load lifts. By letter dated September 5, 2008 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML082410532), the NRC staff transmitted its safety evaluation of the guidelines developed by the Nuclear Energy Institute (NEI) and contained in NEI 08-05, Industry Initiative on Control of Heavy Loads, Revision 0 (ADAMS Accession No. ML082180684). With NRC
staff clarifications and conditions noted in the safety evaluation, licensees may use these guidelines to voluntarily establish a revised licensing basis for handling of reactor vessel heads and other heavy loads that is consistent with the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59, Changes, Tests and Experiments. This RIS requires no action or written response by addressees.


==BACKGROUND INFORMATION==
==BACKGROUND INFORMATION==
By letter dated September 14, 2007 (ADAMS Accession No. ML072670127), NEI notified the NRC staff of plans to implement an industry initiative on heavy load lifts. The initiative resolves a lack of consistency in plant licensing bases that pertain to heavy load handling and ensures that plants continue to conduct heavy load lifts safely.
By letter dated September 14, 2007 (ADAMS Accession No. ML072670127), NEI notified the NRC staff of plans to implement an industry initiative on heavy load lifts. The initiative resolves a lack of consistency in plant licensing bases that pertain to heavy load handling and ensures that plants continue to conduct heavy load lifts safely.


The initiative includes the following actions:  
The initiative includes the following actions:
A) For all heavy load lifts, the initiative specifies adequate implementation of safe load paths, load handling procedures, and industry standards addressing the following topics: training of crane operators, use of special lifting devices, use of slings, and design, inspection, testing, and maintenance of the crane.
        A) For all heavy load lifts, the initiative specifies adequate implementation of safe load paths, load handling procedures, and industry standards addressing the following topics: training of crane operators, use of special lifting devices, use of slings, and design, inspection, testing, and maintenance of the crane.


B) For reactor vessel head lifts and spent fuel cask lifts over the spent fuel pool, the initiative specifies that the licensee use a single-failure-proof crane (or equivalent) or provide a load drop analysis (generic or plant-specific) that bounds the planned lifts with respect to load weight, load height, and medium present under the load. The initiative also specifies that procedures for moving the load reflect the applicable safety basis. Load drop analyses can be based on realistic (i.e., best estimate)  
B) For reactor vessel head lifts and spent fuel cask lifts over the spent fuel pool, the initiative specifies that the licensee use a single-failure-proof crane (or equivalent) or provide a load drop analysis (generic or plant-specific) that bounds the planned lifts with respect to load weight, load height, and medium present under the load. The initiative also specifies that procedures for moving the load reflect the applicable safety basis. Load drop analyses can be based on realistic (i.e., best estimate)
calculations. If the licensee uses load drop analyses, the initiative specifies that plant procedures reflect restrictions on load height, load weight, and medium present under the load.
            calculations. If the licensee uses load drop analyses, the initiative specifies that plant procedures reflect restrictions on load height, load weight, and medium present under the load.


C) The initiative specifies that licensees treat the movement of heavy loads as a configuration management activity in administrative controls established to implement paragraph (a)(4) of 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants."
C) The initiative specifies that licensees treat the movement of heavy loads as a configuration management activity in administrative controls established to implement paragraph (a)(4) of 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.
D) If not already included in the safety analysis report, the initiative specifies that in the next safety analysis report update (after July 1, 2008) the licensee include a summary description of the basis for conducting safe heavy load movements. This description should include the definition of safe load paths, establishment of load handling procedures, and implementation of industry standards addressing the following topics: training of crane operators, use of special lifting devices, use of slings, and design, inspection, testing, and maintenance of cranes. If the safety basis includes reliance on a load drop analysis, then the licensee should include that fact in the summary description of the safety analysis report.
 
D) If not already included in the safety analysis report, the initiative specifies that in the next safety analysis report update (after July 1, 2008) the licensee include a summary description of the basis for conducting safe heavy load movements. This description should include the definition of safe load paths, establishment of load handling procedures, and implementation of industry standards addressing the following topics: training of crane operators, use of special lifting devices, use of slings, and design, inspection, testing, and maintenance of cranes. If the safety basis includes reliance on a load drop analysis, then the licensee should include that fact in the summary description of the safety analysis report.


==SUMMARY OF ISSUE==
==SUMMARY OF ISSUE==
Revision 0 to NEI 08-05 provides industry-developed guidelines for licensee implementation of the voluntary industry heavy loads initiative. To support the initiative, NEI 08-05 includes guidelines for the following activities:  
Revision 0 to NEI 08-05 provides industry-developed guidelines for licensee implementation of the voluntary industry heavy loads initiative. To support the initiative, NEI 08-05 includes guidelines for the following activities:
 
    *   managing the risk associated with maintenance involving movement of heavy loads
* managing the risk associated with maintenance involving movement of heavy loads  
    *   performing consequence analyses for postulated reactor vessel head drops
 
    *   establishing single-failure-proof equivalence for handling systems when used for reactor vessel head lifts
* performing consequence analyses for postulated reactor vessel head drops  
    *   updating the description of heavy load handling programs in the safety analysis report By letter dated September 5, 2008, the NRC staff transmitted its safety evaluation of the guidelines contained in NEI 08-05. The NRC staff considers the acceptance criteria of Appendix F, Rules for Evaluation of Service Loadings with Level D Service Limits, to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III,
 
Division 1, appropriate for evaluation of coolant retaining component performance following a postulated head drop. Otherwise, licensees may consider the guidelines of NEI 08-05 as providing methods approved by the NRC for the specified applications when implementing the requirements of 10 CFR 50.59. With NRC staff clarifications and conditions noted in the safety evaluation, licensees may use these guidelines to voluntarily establish a revised licensing basis for handling of reactor vessel heads and other heavy loads consistent with the provisions of
* establishing single-failure-proof equivalence for handling systems when used for reactor vessel head lifts  
10 CFR 50.59.
 
* updating the description of heavy load handling programs in the safety analysis report By letter dated September 5, 2008, the NRC staff transmitted its safety evaluation of the guidelines contained in NEI 08-05. The NRC staff considers the acceptance criteria of Appendix F, "Rules for Evaluation of Service Loadings with Level D Service Limits," to the American Society of Mechanical Engineer's Boiler and Pressure Vessel Code, Section III, Division 1, appropriate for evaluation of coolant retaining component performance following a postulated head drop. Otherwise, licensees may consider the guidelines of NEI 08-05 as providing methods approved by the NRC for the specified applications when implementing the requirements of 10 CFR 50.59. With NRC staff clarifications and conditions noted in the safety evaluation, licensees may use these guidelines to voluntarily establish a revised licensing basis for handling of reactor vessel heads and other heavy loads consistent with the provisions of 10 CFR 50.59.


Licensees may wish to consider the following regulatory requirements in implementing the industry initiative. Paragraph (a)(4) of 10 CFR 50.65 specifies that licensees assess and manage the increase in risk associated with maintenance activities. The scope of the assessment may be limited to structures, systems and components that a risk-informed evaluation process has shown to be significant to public health and safety. Reactor vessel head removal, in addition to many other heavy load handling activities, could be classified as a maintenance activity. The reactor vessel and attached piping perform a shutdown coolant inventory retention function that is significant to public health and safety. Licensees may determine that some of the commitments related to heavy loads handling at each nuclear power plant serve as measures that limit the increase in risk resulting from heavy load handling. In addition, Appendix A, "Typical Procedures for Pressurized Water Reactors and Boiling Water Reactors," to Regulatory Guide 1.33, "Quality Assurance Program Requirements (Operation)," lists procedures for removal of the reactor head as Item 9.d (6). Accordingly, these procedures may be subject to technical specification administrative control requirements related to the establishment, maintenance, and implementation of these procedures. Finally, the requirements of 10 CFR 50.59 and Paragraph (e) of 10 CFR 50.71, "Maintenance of Records, Making of Reports," apply to changes to the safety analysis report and the content of updates to the safety analysis report, respectively.
Licensees may wish to consider the following regulatory requirements in implementing the industry initiative. Paragraph (a)(4) of 10 CFR 50.65 specifies that licensees assess and manage the increase in risk associated with maintenance activities. The scope of the assessment may be limited to structures, systems and components that a risk-informed evaluation process has shown to be significant to public health and safety. Reactor vessel head removal, in addition to many other heavy load handling activities, could be classified as a maintenance activity. The reactor vessel and attached piping perform a shutdown coolant inventory retention function that is significant to public health and safety. Licensees may determine that some of the commitments related to heavy loads handling at each nuclear power plant serve as measures that limit the increase in risk resulting from heavy load handling. In addition, Appendix A, Typical Procedures for Pressurized Water Reactors and Boiling Water Reactors, to Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation),
lists procedures for removal of the reactor head as Item 9.d (6). Accordingly, these procedures may be subject to technical specification administrative control requirements related to the establishment, maintenance, and implementation of these procedures. Finally, the requirements of 10 CFR 50.59 and Paragraph (e) of 10 CFR 50.71, Maintenance of Records, Making of Reports, apply to changes to the safety analysis report and the content of updates to the safety analysis report, respectively.


==BACKFIT DISCUSSION==
==BACKFIT DISCUSSION==
This RIS notifies addressees of methods described in Revision 0 to NEI 08-05 that the NRC staff has found acceptable for use in evaluating changes to a facility's licensing basis related to reactor vessel head and other heavy load lifts. Licensees may choose to retain the facility's current licensing basis with respect to handling of heavy loads. However, licensee's that choose to clarify the facility's licensing basis with respect to handling of heavy loads consistent with the industry initiative may find that NRC acceptance of the guidelines in NEI 08-05 facilitates the associated changes to the safety analysis report. Pursuant to Paragraph (a)(2)(ii) of 10 CFR 50.59, a change from a method described in the safety analysis report to another method approved by the NRC for the intended application does not constitute a departure from a method of evaluation described in the safety analysis report.
This RIS notifies addressees of methods described in Revision 0 to NEI 08-05 that the NRC
staff has found acceptable for use in evaluating changes to a facilitys licensing basis related to reactor vessel head and other heavy load lifts. Licensees may choose to retain the facilitys current licensing basis with respect to handling of heavy loads. However, licensees that choose to clarify the facilitys licensing basis with respect to handling of heavy loads consistent with the industry initiative may find that NRC acceptance of the guidelines in NEI 08-05 facilitates the associated changes to the safety analysis report. Pursuant to Paragraph (a)(2)(ii)
of 10 CFR 50.59, a change from a method described in the safety analysis report to another method approved by the NRC for the intended application does not constitute a departure from a method of evaluation described in the safety analysis report.


This RIS does not impose any new or modified NRC staff requirements, prescribe any unique way to comply with the regulations, or require any action or written response. Any licensee use of the guidance endorsement referenced by this RIS is strictly voluntary. Therefore, this RIS is not a backfit under 10 CFR 50.109, "Backfitting."  The NRC staff did not perform a backfit analysis.
This RIS does not impose any new or modified NRC staff requirements, prescribe any unique way to comply with the regulations, or require any action or written response. Any licensee use of the guidance endorsement referenced by this RIS is strictly voluntary. Therefore, this RIS is not a backfit under 10 CFR 50.109, Backfitting. The NRC staff did not perform a backfit analysis.


===FEDERAL REGISTER NOTIFICATION===
===FEDERAL REGISTER NOTIFICATION===
A notice of opportunity for public comment on this RIS was not published in the Federal Register because it is informational and pertains to a staff position that does not represent a departure from current regulatory requirements and practice. The NRC interacted with stakeholders in several public meetings, from December 2007 through April 2008, during the development of the industry guidelines contained in Revision 0 to NEI 08-05.
A notice of opportunity for public comment on this RIS was not published in the Federal Register because it is informational and pertains to a staff position that does not represent a departure from current regulatory requirements and practice. The NRC interacted with stakeholders in several public meetings, from December 2007 through April 2008, during the development of the industry guidelines contained in Revision 0 to NEI 08-05.


===CONGRESSIONAL REVIEW ACT===
===CONGRESSIONAL REVIEW ACT===
Line 62: Line 68:


===PAPERWORK REDUCTION ACT STATEMENT===
===PAPERWORK REDUCTION ACT STATEMENT===
This RIS does not contain any information collections and, therefore, is not subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).  
This RIS does not contain any information collections and, therefore, is not subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
  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.
                                    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.
 
/RA/        Timothy McGinty, Director      Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
 
===Technical Contact:===
Steven R. Jones Office of Nuclear Reactor Regulation    (301) 415-2712    E-mail: steve.jones@nrc.gov
 
Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.
 
===CONGRESSIONAL REVIEW ACT===
This is a rule under the Congressional Review Act (5 U.S.C. §§801-808). The Office of Management and Budget (OMB) has determined this is not a major rule.
 
===PAPERWORK REDUCTION ACT STATEMENT===
This RIS does not contain any information collections and, therefore, is not subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
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==
==CONTACT==
Please direct any questions about this matter to the technical contact listed below.
Please direct any questions about this matter to the technical contact listed below.


/RA/       Timothy McGinty, Director       Division of Policy and Rulemaking Office of Nuclear Reactor Regulation  
/RA/
                                              Timothy McGinty, Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation  


===Technical Contact:===
===Technical Contact:===
Steven R. Jones Office of Nuclear Reactor Regulation  
Steven R. Jones Office of Nuclear Reactor Regulation
  (301) 415-2712     E-mail: steve.jones@nrc.gov Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.
                      (301) 415-2712 E-mail: steve.jones@nrc.gov Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.


DISTRIBUTION
RIS: ML082460291 (TAC MD9223)
: RIS File  ADAMS ACCESSION NUMBER:  RIS: ML082460291 (TAC MD9223)
  OFFICE     DSS:NRR         Tech Editor     BC:SBPB:DSS           D:DSS           D:DORL
OFFICE DSS:NRR Tech Editor BC:SBPB:DSS D:DSS D:DORL NAME SJones CHsu MRahimi WRuland JGiitter DATE 09/15/2008 09/03/2008 09/16/2008 09/16/2008 09/17/2008 OFFICE OE BC:APOB:DRA OIS OGC (CRA) OGC (NLO) NAME NHilton MFranovich GTrussell MSmith BMizuno DATE 09/24/2008 09/17/2008 09/29/2008 10/22/2008 09/26/2008 OFFICE PMDA LA:PGCB:DPR:NRRPGCB:DPR:NRR BC:PGCB:DPR:NRR D:DPR:NRR NAME LHill CHawes AWMarkley MMurphy SStuchell for TMcGinty DATE 09/18/2008 11/19/2008 11/19/2008 12/01/2008 12/16/2008 OFFICIAL RECORD
  NAME         SJones           CHsu             MRahimi           WRuland           JGiitter DATE       09/15/2008       09/03/2008         09/16/2008         09/16/2008       09/17/2008 OFFICE         OE         BC:APOB:DRA           OIS             OGC (CRA)       OGC (NLO)
COPY
  NAME         NHilton       MFranovich         GTrussell         MSmith           BMizuno DATE       09/24/2008       09/17/2008         09/29/2008         10/22/2008       09/26/2008 OFFICE       PMDA     LA:PGCB:DPR:NRR    PGCB:DPR:NRR     BC:PGCB:DPR:NRR     D:DPR:NRR
  NAME           LHill         CHawes           AWMarkley       MMurphy SStuchell   TMcGinty for DATE       09/18/2008       11/19/2008         11/19/2008         12/01/2008       12/16/2008
}}
}}


{{RIS-Nav}}
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Latest revision as of 14:29, 14 November 2019

Endorsement of Nuclear Energy Institute Guidance for Reactor Vessel Head Heavy Load Lifts
ML082460291
Person / Time
Issue date: 12/01/2008
From: Mcginty T
Division of Policy and Rulemaking
To:
C HAWES
References
RIS-08-028
Download: ML082460291 (5)
v • d • e


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 December 1, 2008 NRC REGULATORY ISSUE SUMMARY 2008-28 ENDORSEMENT OF NUCLEAR ENERGY INSTITUTE GUIDANCE

FOR REACTOR VESSEL HEAD HEAVY LOAD LIFTS

ADDRESSEES

All holders of operating licenses for nuclear power reactors, except those who 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 notify industry of methods approved by the NRC staff for evaluating changes to a facilitys licensing basis related to reactor vessel head and other heavy load lifts. By letter dated September 5, 2008 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML082410532), the NRC staff transmitted its safety evaluation of the guidelines developed by the Nuclear Energy Institute (NEI) and contained in NEI 08-05, Industry Initiative on Control of Heavy Loads, Revision 0 (ADAMS Accession No. ML082180684). With NRC

staff clarifications and conditions noted in the safety evaluation, licensees may use these guidelines to voluntarily establish a revised licensing basis for handling of reactor vessel heads and other heavy loads that is consistent with the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59, Changes, Tests and Experiments. This RIS requires no action or written response by addressees.

BACKGROUND INFORMATION

By letter dated September 14, 2007 (ADAMS Accession No. ML072670127), NEI notified the NRC staff of plans to implement an industry initiative on heavy load lifts. The initiative resolves a lack of consistency in plant licensing bases that pertain to heavy load handling and ensures that plants continue to conduct heavy load lifts safely.

The initiative includes the following actions:

A) For all heavy load lifts, the initiative specifies adequate implementation of safe load paths, load handling procedures, and industry standards addressing the following topics: training of crane operators, use of special lifting devices, use of slings, and design, inspection, testing, and maintenance of the crane.

B) For reactor vessel head lifts and spent fuel cask lifts over the spent fuel pool, the initiative specifies that the licensee use a single-failure-proof crane (or equivalent) or provide a load drop analysis (generic or plant-specific) that bounds the planned lifts with respect to load weight, load height, and medium present under the load. The initiative also specifies that procedures for moving the load reflect the applicable safety basis. Load drop analyses can be based on realistic (i.e., best estimate)

calculations. If the licensee uses load drop analyses, the initiative specifies that plant procedures reflect restrictions on load height, load weight, and medium present under the load.

C) The initiative specifies that licensees treat the movement of heavy loads as a configuration management activity in administrative controls established to implement paragraph (a)(4) of 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.

D) If not already included in the safety analysis report, the initiative specifies that in the next safety analysis report update (after July 1, 2008) the licensee include a summary description of the basis for conducting safe heavy load movements. This description should include the definition of safe load paths, establishment of load handling procedures, and implementation of industry standards addressing the following topics: training of crane operators, use of special lifting devices, use of slings, and design, inspection, testing, and maintenance of cranes. If the safety basis includes reliance on a load drop analysis, then the licensee should include that fact in the summary description of the safety analysis report.

SUMMARY OF ISSUE

Revision 0 to NEI 08-05 provides industry-developed guidelines for licensee implementation of the voluntary industry heavy loads initiative. To support the initiative, NEI 08-05 includes guidelines for the following activities:

  • managing the risk associated with maintenance involving movement of heavy loads
  • performing consequence analyses for postulated reactor vessel head drops
  • establishing single-failure-proof equivalence for handling systems when used for reactor vessel head lifts
  • updating the description of heavy load handling programs in the safety analysis report By letter dated September 5, 2008, the NRC staff transmitted its safety evaluation of the guidelines contained in NEI 08-05. The NRC staff considers the acceptance criteria of Appendix F, Rules for Evaluation of Service Loadings with Level D Service Limits, to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section III,

Division 1, appropriate for evaluation of coolant retaining component performance following a postulated head drop. Otherwise, licensees may consider the guidelines of NEI 08-05 as providing methods approved by the NRC for the specified applications when implementing the requirements of 10 CFR 50.59. With NRC staff clarifications and conditions noted in the safety evaluation, licensees may use these guidelines to voluntarily establish a revised licensing basis for handling of reactor vessel heads and other heavy loads consistent with the provisions of

10 CFR 50.59.

Licensees may wish to consider the following regulatory requirements in implementing the industry initiative. Paragraph (a)(4) of 10 CFR 50.65 specifies that licensees assess and manage the increase in risk associated with maintenance activities. The scope of the assessment may be limited to structures, systems and components that a risk-informed evaluation process has shown to be significant to public health and safety. Reactor vessel head removal, in addition to many other heavy load handling activities, could be classified as a maintenance activity. The reactor vessel and attached piping perform a shutdown coolant inventory retention function that is significant to public health and safety. Licensees may determine that some of the commitments related to heavy loads handling at each nuclear power plant serve as measures that limit the increase in risk resulting from heavy load handling. In addition, Appendix A, Typical Procedures for Pressurized Water Reactors and Boiling Water Reactors, to Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation),

lists procedures for removal of the reactor head as Item 9.d (6). Accordingly, these procedures may be subject to technical specification administrative control requirements related to the establishment, maintenance, and implementation of these procedures. Finally, the requirements of 10 CFR 50.59 and Paragraph (e) of 10 CFR 50.71, Maintenance of Records, Making of Reports, apply to changes to the safety analysis report and the content of updates to the safety analysis report, respectively.

BACKFIT DISCUSSION

This RIS notifies addressees of methods described in Revision 0 to NEI 08-05 that the NRC

staff has found acceptable for use in evaluating changes to a facilitys licensing basis related to reactor vessel head and other heavy load lifts. Licensees may choose to retain the facilitys current licensing basis with respect to handling of heavy loads. However, licensees that choose to clarify the facilitys licensing basis with respect to handling of heavy loads consistent with the industry initiative may find that NRC acceptance of the guidelines in NEI 08-05 facilitates the associated changes to the safety analysis report. Pursuant to Paragraph (a)(2)(ii)

of 10 CFR 50.59, a change from a method described in the safety analysis report to another method approved by the NRC for the intended application does not constitute a departure from a method of evaluation described in the safety analysis report.

This RIS does not impose any new or modified NRC staff requirements, prescribe any unique way to comply with the regulations, or require any action or written response. Any licensee use of the guidance endorsement referenced by this RIS is strictly voluntary. Therefore, this RIS is not a backfit under 10 CFR 50.109, Backfitting. The NRC staff did not perform a backfit analysis.

FEDERAL REGISTER NOTIFICATION

A notice of opportunity for public comment on this RIS was not published in the Federal Register because it is informational and pertains to a staff position that does not represent a departure from current regulatory requirements and practice. The NRC interacted with stakeholders in several public meetings, from December 2007 through April 2008, during the development of the industry guidelines contained in Revision 0 to NEI 08-05.

CONGRESSIONAL REVIEW ACT

This is a rule under the Congressional Review Act (5 U.S.C. §§801-808). The Office of Management and Budget (OMB) has determined this is not a major rule.

PAPERWORK REDUCTION ACT STATEMENT

This RIS does not contain any information collections and, therefore, is not subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).

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.

/RA/

Timothy McGinty, Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

Technical Contact:

Steven R. Jones Office of Nuclear Reactor Regulation

(301) 415-2712 E-mail: steve.jones@nrc.gov Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.

RIS: ML082460291 (TAC MD9223)

OFFICE DSS:NRR Tech Editor BC:SBPB:DSS D:DSS D:DORL

NAME SJones CHsu MRahimi WRuland JGiitter DATE 09/15/2008 09/03/2008 09/16/2008 09/16/2008 09/17/2008 OFFICE OE BC:APOB:DRA OIS OGC (CRA) OGC (NLO)

NAME NHilton MFranovich GTrussell MSmith BMizuno DATE 09/24/2008 09/17/2008 09/29/2008 10/22/2008 09/26/2008 OFFICE PMDA LA:PGCB:DPR:NRR PGCB:DPR:NRR BC:PGCB:DPR:NRR D:DPR:NRR

NAME LHill CHawes AWMarkley MMurphy SStuchell TMcGinty for DATE 09/18/2008 11/19/2008 11/19/2008 12/01/2008 12/16/2008


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