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| number = ML18022A109
| number = ML18022A109
| issue date = 01/19/2018
| issue date = 01/19/2018
| title = Request for Additional Information Regarding Fermi RR-A37
| title = NRR E-mail Capture - Request for Additional Information Regarding Fermi RR-A37
| author name = Goetz S
| author name = Goetz S
| author affiliation = NRC/NRR/DORL/LPLIII
| author affiliation = NRC/NRR/DORL/LPLIII
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:1 NRR-DMPSPEm Resource From:Goetz, Sujata Sent: Friday, January 19, 2018 11:44 AM To: Jason R Haas
{{#Wiki_filter:NRR-DMPSPEm Resource From:                             Goetz, Sujata Sent:                             Friday, January 19, 2018 11:44 AM To:                               Jason R Haas


==Subject:==
==Subject:==
Request for Additional Information Regarding Fermi RR-A37 Attachments:
Request for Additional Information Regarding Fermi RR-A37 Attachments:                     RAI 2.docx Mr. Haas, In a letter dated September 26, 2017, (Agencywide Documents Access and Management System Accession No. ML17270A036), the DTE Electric Company submitted relief request number A-37.
RAI 2.docx Mr. Haas, In a letter dated September 26, 2017, (Agencywide Documents Access and Management System Accession No. ML17270A036), the DTE Electric Company submitted relief request number A-37.
The relief request is regarding the implementation of ASME Code Case N-702, Alternative Requirements for Boiling Water Reactor Nozzle Inner Radius and Nozzle-to-Shell Welds, Section XI, Division 1, and Boiling Water Reactor Vessel Inspection Program-241, Probabilistic Fracture Mechanics Evaluation for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii.
The relief request is regarding the implementation of ASME Code Case N-702, "Alternative Requirements for Boiling Water Reactor Nozzle Inner Radius and Nozzle-to-Shell Welds, Section XI, Division 1," and Boiling Water Reactor Vessel Inspection Program-241, "Probabilistic Fracture Mechanics Evaluation for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii."
The Nuclear Regulatory Commission staff has reviewed your submittal and has determined that additional information, as stated in the attachment to this email, is needed to complete its review.
The Nuclear Regulatory Commission staff has reviewed your submittal and has determined that additional  
 
information
, as stated in the attachment to this email, is needed to complete its review.
 
Please let me know if you would like to schedule a clarification call. Your response to the NRC is due by February 19, 2018.
Please let me know if you would like to schedule a clarification call. Your response to the NRC is due by February 19, 2018.
Sujata Goetz Project Manager, Fermi, Unit 2  
Sujata Goetz Project Manager, Fermi, Unit 2 Nuclear Regulatory Commission 11555 Rockville Pike Office of the Nuclear Reactor Regulation NRC/NRR/DORL/LPL3 Office O8F2 Mailroom O8-B1A Rockville, MD 20852-2738 Washington, DC 20555-0001 (o) 301.415.8004 (f) 301.415.3313 1
 
Nuclear Regulatory Commission 11555 Rockville Pike Office of the Nuclear Reactor Regulation NRC/NRR/DORL/LPL3  
 
Office O8F2 Mailroom O8-B1A Rockville, MD 20852-2738 Washington, DC 20555-0001  
 
(o) 301.415.8004 (f) 301.415.3313  


Hearing Identifier: NRR_DMPS Email Number: 109   Mail Envelope Properties  (BN6PR09MB2274E384DD8EDC5A4BFE3D6A80EF0)
Hearing Identifier:   NRR_DMPS Email Number:         109 Mail Envelope Properties  (BN6PR09MB2274E384DD8EDC5A4BFE3D6A80EF0)


==Subject:==
==Subject:==
Request for Additional Information Regarding Fermi RR-A37 Sent Date:   1/19/2018 11:44:07 AM Received Date: 1/19/2018 11:44:08 AM From:   Goetz, Sujata Created By:   Sujata.Goetz@nrc.gov Recipients:     "Jason R Haas" <jason.haas@dteenergy.com>
Request for Additional Information Regarding Fermi RR-A37 Sent Date:           1/19/2018 11:44:07 AM Received Date:       1/19/2018 11:44:08 AM From:                 Goetz, Sujata Created By:           Sujata.Goetz@nrc.gov Recipients:
Tracking Status: None  
"Jason R Haas" <jason.haas@dteenergy.com>
 
Tracking Status: None Post Office:         BN6PR09MB2274.namprd09.prod.outlook.com Files                         Size                       Date & Time MESSAGE                       1212                     1/19/2018 11:44:08 AM RAI 2.docx                   19075 Options Priority:                     Standard Return Notification:         No Reply Requested:             No Sensitivity:                 Normal Expiration Date:
Post Office:   BN6PR09MB2274.namprd09.prod.outlook.com Files     Size     Date & Time MESSAGE   1212     1/19/2018 11:44:08 AM RAI 2.docx   19075 Options Priority:     Standard   Return Notification:   No   Reply Requested:   No   Sensitivity:     Normal Expiration Date:     Recipients Received:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF - RR-A37, REVISION 1 FERMI 2 DOCKET NO. 50-341 Electric Power Research Institute, Technical Report 1003557, "BWRVIP [Boiling Water reactor Vessel and Internal Project] -108, "Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radii" and Topical Report BWRVIP-241, "Probabilistic Fracture Mechanics [PFM] Evaluation for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii" contain PFM analysis results supporting Code Case N-702. BWRVIP-241 contains additional PFM results supporting revision of the evaluation criteria under "Conditions and Limitations" in the safety evaluation (SE) for BWRVIP-108. Section 3 of BWRVIP-108 states that CRD nozzles are eliminated from consideration since they are not full penetration welds. The staff's SE for BWRVIP-108, dated December 19, 2007 (ADAMS Accession No. ML073600374) states the report considered nozzles which are joined with full penetration welds and as a result, the CRD nozzles, which use partial penetration welds, are outside the scope of the report. Furthermore, ASME Code Case N-702 states, in part, that it excludes the control rod drive return line nozzles.
 
In Attachment 2 of the licensee's letter dated September 26, 2017, in the table "Applicable Components," the licensee included the N10 nozzle, ID# 15-315 IRS, "CRD Nozzle Inside Radius Section" and N10 Nozzle, ID# 15-315, "CRD Nozzle-to-Vessel Weld in its list of components affected."  Based on the staff's review of the licensee's application, the inclusion of the N10 nozzle from the CRD System is inconsistent with ASME Code Case N-702, BWRVIP-108 and BWRVIP-241 criteria. In order to expand the scope of BWRVIP-108 and BWRVIP-241 to include the CRD nozzles in the submittal, the licensee would need submit an analysis similar to the one provided in BWRVIP-108 and considers all stresses, including the
 
reduced thermal fatigue stresses and use assumptions relevant to the CRD nozzles.


REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF - RR-A37, REVISION 1 FERMI 2 DOCKET NO. 50-341 Electric Power Research Institute, Technical Report 1003557, BWRVIP [Boiling Water reactor Vessel and Internal Project] -108, Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radii and Topical Report BWRVIP-241, Probabilistic Fracture Mechanics [PFM] Evaluation for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii contain PFM analysis results supporting Code Case N-702. BWRVIP-241 contains additional PFM results supporting revision of the evaluation criteria under Conditions and Limitations in the safety evaluation (SE) for BWRVIP-108. Section 3 of BWRVIP-108 states that CRD nozzles are eliminated from consideration since they are not full penetration welds. The staffs SE for BWRVIP-108, dated December 19, 2007 (ADAMS Accession No. ML073600374) states the report considered nozzles which are joined with full penetration welds and as a result, the CRD nozzles, which use partial penetration welds, are outside the scope of the report. Furthermore, ASME Code Case N-702 states, in part, that it excludes the control rod drive return line nozzles.
In Attachment 2 of the licensees letter dated September 26, 2017, in the table Applicable Components, the licensee included the N10 nozzle, ID# 15-315 IRS, CRD Nozzle Inside Radius Section and N10 Nozzle, ID# 15-315, CRD Nozzle-to-Vessel Weld in its list of components affected. Based on the staffs review of the licensees application, the inclusion of the N10 nozzle from the CRD System is inconsistent with ASME Code Case N-702, BWRVIP-108 and BWRVIP-241 criteria. In order to expand the scope of BWRVIP-108 and BWRVIP-241 to include the CRD nozzles in the submittal, the licensee would need submit an analysis similar to the one provided in BWRVIP-108 and considers all stresses, including the reduced thermal fatigue stresses and use assumptions relevant to the CRD nozzles.
Please justify the inclusion of the N10 nozzle from the CRD System in this Relief Request for the use of the proposed alternative in Code Case N-702. Alternatively, remove N10 nozzle from the list of applicable components from your application.}}
Please justify the inclusion of the N10 nozzle from the CRD System in this Relief Request for the use of the proposed alternative in Code Case N-702. Alternatively, remove N10 nozzle from the list of applicable components from your application.}}

Latest revision as of 16:35, 2 December 2019

NRR E-mail Capture - Request for Additional Information Regarding Fermi RR-A37
ML18022A109
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 01/19/2018
From: Sujata Goetz
Plant Licensing Branch III
To: Jonathan Haas
DTE Energy
References
Download: ML18022A109 (3)
v • d • e


Text

NRR-DMPSPEm Resource From: Goetz, Sujata Sent: Friday, January 19, 2018 11:44 AM To: Jason R Haas

Subject:

Request for Additional Information Regarding Fermi RR-A37 Attachments: RAI 2.docx Mr. Haas, In a letter dated September 26, 2017, (Agencywide Documents Access and Management System Accession No. ML17270A036), the DTE Electric Company submitted relief request number A-37.

The relief request is regarding the implementation of ASME Code Case N-702, Alternative Requirements for Boiling Water Reactor Nozzle Inner Radius and Nozzle-to-Shell Welds,Section XI, Division 1, and Boiling Water Reactor Vessel Inspection Program-241, Probabilistic Fracture Mechanics Evaluation for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii.

The Nuclear Regulatory Commission staff has reviewed your submittal and has determined that additional information, as stated in the attachment to this email, is needed to complete its review.

Please let me know if you would like to schedule a clarification call. Your response to the NRC is due by February 19, 2018.

Sujata Goetz Project Manager, Fermi, Unit 2 Nuclear Regulatory Commission 11555 Rockville Pike Office of the Nuclear Reactor Regulation NRC/NRR/DORL/LPL3 Office O8F2 Mailroom O8-B1A Rockville, MD 20852-2738 Washington, DC 20555-0001 (o) 301.415.8004 (f) 301.415.3313 1

Hearing Identifier: NRR_DMPS Email Number: 109 Mail Envelope Properties (BN6PR09MB2274E384DD8EDC5A4BFE3D6A80EF0)

Subject:

Request for Additional Information Regarding Fermi RR-A37 Sent Date: 1/19/2018 11:44:07 AM Received Date: 1/19/2018 11:44:08 AM From: Goetz, Sujata Created By: Sujata.Goetz@nrc.gov Recipients:

"Jason R Haas" <jason.haas@dteenergy.com>

Tracking Status: None Post Office: BN6PR09MB2274.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1212 1/19/2018 11:44:08 AM RAI 2.docx 19075 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF - RR-A37, REVISION 1 FERMI 2 DOCKET NO. 50-341 Electric Power Research Institute, Technical Report 1003557, BWRVIP [Boiling Water reactor Vessel and Internal Project] -108, Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radii and Topical Report BWRVIP-241, Probabilistic Fracture Mechanics [PFM] Evaluation for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii contain PFM analysis results supporting Code Case N-702. BWRVIP-241 contains additional PFM results supporting revision of the evaluation criteria under Conditions and Limitations in the safety evaluation (SE) for BWRVIP-108. Section 3 of BWRVIP-108 states that CRD nozzles are eliminated from consideration since they are not full penetration welds. The staffs SE for BWRVIP-108, dated December 19, 2007 (ADAMS Accession No. ML073600374) states the report considered nozzles which are joined with full penetration welds and as a result, the CRD nozzles, which use partial penetration welds, are outside the scope of the report. Furthermore, ASME Code Case N-702 states, in part, that it excludes the control rod drive return line nozzles.

In Attachment 2 of the licensees letter dated September 26, 2017, in the table Applicable Components, the licensee included the N10 nozzle, ID# 15-315 IRS, CRD Nozzle Inside Radius Section and N10 Nozzle, ID# 15-315, CRD Nozzle-to-Vessel Weld in its list of components affected. Based on the staffs review of the licensees application, the inclusion of the N10 nozzle from the CRD System is inconsistent with ASME Code Case N-702, BWRVIP-108 and BWRVIP-241 criteria. In order to expand the scope of BWRVIP-108 and BWRVIP-241 to include the CRD nozzles in the submittal, the licensee would need submit an analysis similar to the one provided in BWRVIP-108 and considers all stresses, including the reduced thermal fatigue stresses and use assumptions relevant to the CRD nozzles.

Please justify the inclusion of the N10 nozzle from the CRD System in this Relief Request for the use of the proposed alternative in Code Case N-702. Alternatively, remove N10 nozzle from the list of applicable components from your application.

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