ML18053A149: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:March 6, 2018  
{{#Wiki_filter:March 6, 2018 Mr. W. Anthony Nowinowski, Program Manager PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive, Suite 380 Cranberry Township, PA 16066
 
Mr. W. Anthony Nowinowski, Program Manager PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive, Suite 380 Cranberry Township, PA 16066  


==SUBJECT:==
==SUBJECT:==
ACCEPTANCE FOR REVIEW OF THE PRESSURIZED WATER REACTOR OWNERS GROUP TOPICAL REPORT BAW-2178-P, SUPPLEMENT 1, REVISION 0, LOW UPPER-SHELF TOUGHNESS FRACTURE MECHANICS ANALYSIS OF REACTOR VESSELS OF B&W OWNERS REACTOR VESSEL WORKING GROUP FOR LEVELS C & D SERVICE LOADS
ACCEPTANCE FOR REVIEW OF THE PRESSURIZED WATER REACTOR OWNERS GROUP TOPICAL REPORT BAW-2178-P, SUPPLEMENT 1, REVISION 0, LOW UPPER-SHELF TOUGHNESS FRACTURE MECHANICS ANALYSIS OF REACTOR VESSELS OF B&W OWNERS REACTOR VESSEL WORKING GROUP FOR LEVELS C & D SERVICE LOADS


==Dear Mr. Nowinowski:==
==Dear Mr. Nowinowski:==


By letter dated December 15, 2017 (Agencywide Documents Access and Management System Accession No. ML17354A011), the Pressurized Water Reactor Owners Group (PWROG) submitted Topical Report (TR) BAW-2178-P, Supplement 1, Revision 0, "Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels C & D Service Loads," to the U.S. Nuclear Regulatory Commission (NRC) staff for review.  
By letter dated December 15, 2017 (Agencywide Documents Access and Management System Accession No. ML17354A011), the Pressurized Water Reactor Owners Group (PWROG) submitted Topical Report (TR) BAW-2178-P, Supplement 1, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels C & D Service Loads, to the U.S. Nuclear Regulatory Commission (NRC) staff for review.
 
The NRC staff has found that the material presented is sufficient to begin our review. The NRC staff expects to issue its request for additional information by June 1, 2018, and issue its draft safety evaluation (SE) in August 2018. This schedule information takes in consideration the NRCs current review priorities and available technical resources and may be subject to change.
The NRC staff has found that the material presented is sufficient to begin our review. The NRC staff expects to issue its request for additional information by June 1, 2018, and issue its draft safety evaluation (SE) in August 2018. This schedule information takes in consideration the NRC's current review priorities and available technical resources and may be subject to change. If modifications to these dates are deemed necessary, we will provide appropriate updates to this information. Section 170.21 of Title 10 of the Code of Federal Regulations requires that TRs are subject to fees based on the full cost of the review.  
If modifications to these dates are deemed necessary, we will provide appropriate updates to this information. Section 170.21 of Title 10 of the Code of Federal Regulations requires that TRs are subject to fees based on the full cost of the review.
 
As with all TRs, the SE will be reviewed by the NRCs Office of the General Counsel (OGC) to determine whether it falls within the scope of the Congressional Review Act (CRA). During the course of this review, OGC considers whether any endorsement or acceptance of a TR by the NRC amounts to a rule as defined in the CRA. If this initial review concludes that the SE, with its accompanying TR, may be a rule, the NRC will forward the package to the Office of Management and Budget (OMB) for further review and consideration. Any review by OMB would impact the schedule for the issuance of the final SE.
As with all TRs, the SE will be reviewed by the NRC's Office of the General Counsel (OGC) to determine whether it falls within the scope of the Congressional Review Act (CRA). During the course of this review, OGC considers whether any endorsement or acceptance of a TR by the NRC amounts to a rule as defined in the CRA. If this initial review concludes that the SE, with its accompanying TR, may be a rule, the NRC will forward the package to the Office of Management and Budget (OMB) for further review and consideration. Any review by OMB would impact the schedule for the issuance of the final SE.  


W. If you have questions regarding this matter, please contact Brian Benney at (301) 415-2767.
W. A. Nowinowski                                If you have questions regarding this matter, please contact Brian Benney at (301) 415-2767.
Sincerely,         /RA/   Dennis Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902037
Sincerely,
                                                    /RA/
Dennis Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902037


ML18053A149; *concurred via e-mail   NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DE/EMIB/BC* NAME BBenney DHarrison SRuffin DATE 3/5/18 2/27/18 2/26/18 OFFICE NRR/DLP/PLPB/BC NAME DMorey DATE 3/6/18}}
ML18053A149; *concurred via e-mail           NRR-106 OFFICE     NRR/DLP/PLPB/PM         NRR/DLP/PLPB/LA*   NRR/DE/EMIB/BC*
NAME       BBenney                 DHarrison           SRuffin DATE       3/5/18                 2/27/18             2/26/18 OFFICE     NRR/DLP/PLPB/BC NAME       DMorey DATE       3/6/18}}

Latest revision as of 20:21, 21 October 2019

Acceptance for Review of the Pressurized Water Reactor Owners Group Topical Report BAW-2178-P, Supplement 1, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessel of B&W Owners Reactor Vessel Working Group for
ML18053A149
Person / Time
Site: PROJ0694, 99902037
Issue date: 03/06/2018
From: Dennis Morey
NRC/NRR/DLP/PLPB
To: Nowinowski W
Westinghouse
Benney B
References
BAW-2178-P
Download: ML18053A149 (3)


Text

March 6, 2018 Mr. W. Anthony Nowinowski, Program Manager PWR Owners Group, Program Management Office Westinghouse Electric Company 1000 Westinghouse Drive, Suite 380 Cranberry Township, PA 16066

SUBJECT:

ACCEPTANCE FOR REVIEW OF THE PRESSURIZED WATER REACTOR OWNERS GROUP TOPICAL REPORT BAW-2178-P, SUPPLEMENT 1, REVISION 0, LOW UPPER-SHELF TOUGHNESS FRACTURE MECHANICS ANALYSIS OF REACTOR VESSELS OF B&W OWNERS REACTOR VESSEL WORKING GROUP FOR LEVELS C & D SERVICE LOADS

Dear Mr. Nowinowski:

By letter dated December 15, 2017 (Agencywide Documents Access and Management System Accession No. ML17354A011), the Pressurized Water Reactor Owners Group (PWROG) submitted Topical Report (TR) BAW-2178-P, Supplement 1, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels C & D Service Loads, to the U.S. Nuclear Regulatory Commission (NRC) staff for review.

The NRC staff has found that the material presented is sufficient to begin our review. The NRC staff expects to issue its request for additional information by June 1, 2018, and issue its draft safety evaluation (SE) in August 2018. This schedule information takes in consideration the NRCs current review priorities and available technical resources and may be subject to change.

If modifications to these dates are deemed necessary, we will provide appropriate updates to this information. Section 170.21 of Title 10 of the Code of Federal Regulations requires that TRs are subject to fees based on the full cost of the review.

As with all TRs, the SE will be reviewed by the NRCs Office of the General Counsel (OGC) to determine whether it falls within the scope of the Congressional Review Act (CRA). During the course of this review, OGC considers whether any endorsement or acceptance of a TR by the NRC amounts to a rule as defined in the CRA. If this initial review concludes that the SE, with its accompanying TR, may be a rule, the NRC will forward the package to the Office of Management and Budget (OMB) for further review and consideration. Any review by OMB would impact the schedule for the issuance of the final SE.

W. A. Nowinowski If you have questions regarding this matter, please contact Brian Benney at (301) 415-2767.

Sincerely,

/RA/

Dennis Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation Docket No. 99902037

ML18053A149; *concurred via e-mail NRR-106 OFFICE NRR/DLP/PLPB/PM NRR/DLP/PLPB/LA* NRR/DE/EMIB/BC*

NAME BBenney DHarrison SRuffin DATE 3/5/18 2/27/18 2/26/18 OFFICE NRR/DLP/PLPB/BC NAME DMorey DATE 3/6/18