ML18130A050: Difference between revisions

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| issue date = 06/26/2018
| issue date = 06/26/2018
| title = Transmittal Letter Regarding Final Proprietary Safety Evaluation for Electric Power Research Institute Topical Report BWRVIP-41, Revision 4, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines (CAC No. MF4887; EPID L-2014-TOP-00
| title = Transmittal Letter Regarding Final Proprietary Safety Evaluation for Electric Power Research Institute Topical Report BWRVIP-41, Revision 4, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines (CAC No. MF4887; EPID L-2014-TOP-00
| author name = Morey D C
| author name = Morey D
| author affiliation = NRC/NRR/DLP/PLPB
| author affiliation = NRC/NRR/DLP/PLPB
| addressee name = Hanley T K
| addressee name = Hanley T
| addressee affiliation = Electric Power Research Institute (EPRI)
| addressee affiliation = Electric Power Research Institute (EPRI)
| docket = 99902016
| docket = 99902016
| license number =  
| license number =  
| contact person = Holonich J J
| contact person = Holonich J
| case reference number = CAC MF4887, EPID L-2014-TOP-0008
| case reference number = CAC MF4887, EPID L-2014-TOP-0008
| document type = Final Safety Evaluation Report (FSER), Letter
| document type = Final Safety Evaluation Report (FSER), Letter
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=Text=
=Text=
{{#Wiki_filter:/RA/}}
{{#Wiki_filter:OFFICIAL USE ONLY - PROPRIETARY INFORMATION T. Hanley                                                                                June 26, 2018 Mr. Tim Hanley Senior Vice President West Operations, Exelon Chairman, BWR Vessel and Internals Project 3420 Hillview Avenue Palo Alto, CA 94304-1395
 
==SUBJECT:==
FINAL PROPRIETARY SAFETY EVALUATION FOR ELECTRIC POWER RESEARCH INSTITUTE TOPICAL REPORT BWRVIP-41, REVISION 4, BWR JET PUMP ASSEMBLY INSPECTION AND FLAW EVALUATION GUIDELINES (CAC NO. MF4887; EPID L-2014-TOP-0008)
 
==Dear Mr. Hanley:==
 
By letter dated September 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14279A437), the Boiling Water Reactor (BWR) Vessel and Internals Program (BWRVIP) submitted for U.S. Nuclear Regulatory Commission (NRC) staff review the Topical Report (TR) BWRVIP-41, Revision 4, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines. By letter dated April 20, 2018, the NRC staff issued its draft safety evaluation (SE) on BWRVIP-41, Revision 4 (ADAMS Accession No. ML17171A317).
By letter dated May 9, 2018 (ADAMS Accession No. ML18131A164), the BWRVIP provided comments on the NRC draft SE. The comments provided by the BWRVIP were related to the identification of proprietary information in the draft SE, clarifications and accuracy.
The NRC staff has found that BWRVIP-41, Revision 4 is acceptable for referencing in licensing applications for nuclear power plants to the extent specified and under the limitations delineated in the TR and in the enclosed final SE. The final SE defines the basis for our acceptance of the TR.
Our acceptance applies only to material provided in the subject TR. We do not intend to repeat our review of the acceptable material described in the TR. When the TR appears as a reference in license applications, our review will ensure that the material presented applies to the specific plant involved. License amendment requests that deviate from this TR will be subject to a plant-specific review in accordance with applicable review standards.
NOTICE: Enclosure transmitted herewith contains Proprietary Information. When separated from enclosure, this transmittal document is decontrolled.
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
 
OFFICIAL USE ONLY - PROPRIETARY INFORMATION In accordance with the guidance provided on the NRC website, we request that EPRI publish approved proprietary and non-proprietary versions of TR BWRVIP-41, Revision 4 within six months of receipt of this letter. The approved versions shall incorporate this letter and the enclosed final SE after the title page. Also, they must contain historical review information, including NRC requests for additional information and your responses. The approved versions shall include an -A (designating approved) following the TR identification symbol.
As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TRs were provided to the NRC staff to support the resolution of RAI responses and the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs:
: 1. The RAIs and RAI responses can be included as an Appendix to the accepted version.
: 2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR.
If future changes to the NRCs regulatory requirements affect the acceptability of this TR, EPRI will be expected to revise the TR appropriately. Licensees referencing this TR would be expected to justify its continued applicability or evaluate their plant using the revised TR.
If you have any questions or require any additional information, please feel free to contact the NRC Project Manager for the review, Joseph Holonich at (301) 415-7297 or joseph.holonich@nrc.gov.
Sincerely,
                                                /RA/
Dennis C. Morey, Chief Licensing Processes Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 99902016
 
==Enclosure:==
 
Final Safety Evaluation OFFICIAL USE ONLY - PROPRIETARY INFORMATION
 
Package ML18130A023 Transmittal Letter ML18130A050 Proprietary SE ML18129A054            *via e-mail                    NRR-106 OFFICE      DLP/PLPB/PM^          DLP/PLPB/LA*          DMLR/MPHB/BC*
NAME        JHolonich            DHarrison            DAlley DATE      6/22/18                6/21/18              6/7/18 OFFICE      DE/DMLR/MVIB*        DLP/PLPB/BC NAME      SRuffin                DMorey DATE      6/21/18                6/26/18}}

Latest revision as of 05:28, 21 October 2019

Transmittal Letter Regarding Final Proprietary Safety Evaluation for Electric Power Research Institute Topical Report BWRVIP-41, Revision 4, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines (CAC No. MF4887; EPID L-2014-TOP-00
ML18130A050
Person / Time
Site: 99902016
Issue date: 06/26/2018
From: Dennis Morey
NRC/NRR/DLP/PLPB
To: Hanley T
Electric Power Research Institute
Holonich J
References
CAC MF4887, EPID L-2014-TOP-0008
Download: ML18130A050 (3)


Text

OFFICIAL USE ONLY - PROPRIETARY INFORMATION T. Hanley June 26, 2018 Mr. Tim Hanley Senior Vice President West Operations, Exelon Chairman, BWR Vessel and Internals Project 3420 Hillview Avenue Palo Alto, CA 94304-1395

SUBJECT:

FINAL PROPRIETARY SAFETY EVALUATION FOR ELECTRIC POWER RESEARCH INSTITUTE TOPICAL REPORT BWRVIP-41, REVISION 4, BWR JET PUMP ASSEMBLY INSPECTION AND FLAW EVALUATION GUIDELINES (CAC NO. MF4887; EPID L-2014-TOP-0008)

Dear Mr. Hanley:

By letter dated September 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14279A437), the Boiling Water Reactor (BWR) Vessel and Internals Program (BWRVIP) submitted for U.S. Nuclear Regulatory Commission (NRC) staff review the Topical Report (TR) BWRVIP-41, Revision 4, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines. By letter dated April 20, 2018, the NRC staff issued its draft safety evaluation (SE) on BWRVIP-41, Revision 4 (ADAMS Accession No. ML17171A317).

By letter dated May 9, 2018 (ADAMS Accession No. ML18131A164), the BWRVIP provided comments on the NRC draft SE. The comments provided by the BWRVIP were related to the identification of proprietary information in the draft SE, clarifications and accuracy.

The NRC staff has found that BWRVIP-41, Revision 4 is acceptable for referencing in licensing applications for nuclear power plants to the extent specified and under the limitations delineated in the TR and in the enclosed final SE. The final SE defines the basis for our acceptance of the TR.

Our acceptance applies only to material provided in the subject TR. We do not intend to repeat our review of the acceptable material described in the TR. When the TR appears as a reference in license applications, our review will ensure that the material presented applies to the specific plant involved. License amendment requests that deviate from this TR will be subject to a plant-specific review in accordance with applicable review standards.

NOTICE: Enclosure transmitted herewith contains Proprietary Information. When separated from enclosure, this transmittal document is decontrolled.

OFFICIAL USE ONLY - PROPRIETARY INFORMATION

OFFICIAL USE ONLY - PROPRIETARY INFORMATION In accordance with the guidance provided on the NRC website, we request that EPRI publish approved proprietary and non-proprietary versions of TR BWRVIP-41, Revision 4 within six months of receipt of this letter. The approved versions shall incorporate this letter and the enclosed final SE after the title page. Also, they must contain historical review information, including NRC requests for additional information and your responses. The approved versions shall include an -A (designating approved) following the TR identification symbol.

As an alternative to including the RAIs and RAI responses behind the title page, if changes to the TRs were provided to the NRC staff to support the resolution of RAI responses and the NRC staff reviewed and approved those changes as described in the RAI responses, there are two ways that the accepted version can capture the RAIs:

1. The RAIs and RAI responses can be included as an Appendix to the accepted version.
2. The RAIs and RAI responses can be captured in the form of a table (inserted after the final SE) which summarizes the changes as shown in the approved version of the TR. The table should reference the specific RAIs and RAI responses which resulted in any changes, as shown in the accepted version of the TR.

If future changes to the NRCs regulatory requirements affect the acceptability of this TR, EPRI will be expected to revise the TR appropriately. Licensees referencing this TR would be expected to justify its continued applicability or evaluate their plant using the revised TR.

If you have any questions or require any additional information, please feel free to contact the NRC Project Manager for the review, Joseph Holonich at (301) 415-7297 or joseph.holonich@nrc.gov.

Sincerely,

/RA/

Dennis C. Morey, Chief Licensing Processes Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 99902016

Enclosure:

Final Safety Evaluation OFFICIAL USE ONLY - PROPRIETARY INFORMATION

Package ML18130A023 Transmittal Letter ML18130A050 Proprietary SE ML18129A054 *via e-mail NRR-106 OFFICE DLP/PLPB/PM^ DLP/PLPB/LA* DMLR/MPHB/BC*

NAME JHolonich DHarrison DAlley DATE 6/22/18 6/21/18 6/7/18 OFFICE DE/DMLR/MVIB* DLP/PLPB/BC NAME SRuffin DMorey DATE 6/21/18 6/26/18