ML14017A042: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 3: Line 3:
| issue date = 01/29/2014
| issue date = 01/29/2014
| title = Acceptance Letter Regarding End of Interval Relief Requests Associated with the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF3406 and MF3407)
| title = Acceptance Letter Regarding End of Interval Relief Requests Associated with the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF3406 and MF3407)
| author name = Khanna M K
| author name = Khanna M
| author affiliation = NRC/NRR/DORL/LPLI-2
| author affiliation = NRC/NRR/DORL/LPLI-2
| addressee name = Pacilio M J
| addressee name = Pacilio M
| addressee affiliation = Exelon Nuclear
| addressee affiliation = Exelon Nuclear
| docket = 05000219
| docket = 05000219
| license number =  
| license number =  
| contact person = Lamb J G
| contact person = Lamb J
| case reference number = TAC MF3406, TAC MF3407
| case reference number = TAC MF3406, TAC MF3407
| document type = Letter
| document type = Letter
Line 24: Line 24:


==Dear Mr. Pacilio:==
==Dear Mr. Pacilio:==
By letter dated January 7, 2014 (Agencywide Documents Access and Management System Accession No. ML 14017A042), Exelon Generation Company, LLC submitted relief requests (RRs) from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components." These RRs apply to the fourth 1 0-year lnservice Inspection (lSI) interval, which concluded on January 14, 2013, for the Oyster Creek Nuclear Generating Station. The fourth 1 0-year lSI interval complied with the ASME B&PV Code, Section XI, 1995 Edition with 1996 Addenda. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of these RRs. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations, the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the M. Pacilio environment.
By letter dated January 7, 2014 (Agencywide Documents Access and Management System Accession No. ML14017A042), Exelon Generation Company, LLC submitted relief requests (RRs) from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components." These RRs apply to the fourth 1 0-year lnservice Inspection (lSI) interval, which concluded on January 14, 2013, for the Oyster Creek Nuclear Generating Station. The fourth 1 0-year lSI interval complied with the ASME B&PV Code, Section XI, 1995 Edition with 1996 Addenda. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of these RRs. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations, the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the M. Pacilio environment.
If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-3100 or by email at John.Lamb@nrc.gov.
If you have any questions, please contact me at (301) 415-3100 or by email at John.Lamb@nrc.gov.
Line 31: Line 31:
If you have any questions, please contact me at (301) 415-3100 or by email at John. Lamb@nrc.gov.
If you have any questions, please contact me at (301) 415-3100 or by email at John. Lamb@nrc.gov.
Docket No. 50-219 cc: Distribution via Listserv DISTRIBUTION:
Docket No. 50-219 cc: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrLAABaxter Resource RidsNrrPMOysterCreek Resource RidsNrrDoriDpr Resource RidsNrrDeEeeb Resource RidsAcrsAcnw_MaiiCTR Resource Sincerely, Ira/ Meena Khanna, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNRRDorllpl1-2 Resource RidsNrrDirsltsb Resource RidsRgn1 MaiiCenter Resource LPLI-2 RIF ADAMS Accession No: ML 14017A042
PUBLIC RidsNrrLAABaxter Resource RidsNrrPMOysterCreek Resource RidsNrrDoriDpr Resource RidsNrrDeEeeb Resource RidsAcrsAcnw_MaiiCTR Resource Sincerely, Ira/ Meena Khanna, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNRRDorllpl1-2 Resource RidsNrrDirsltsb Resource RidsRgn1 MaiiCenter Resource LPLI-2 RIF ADAMS Accession No: ML14017A042
*via email OFFICE NRR/DORLILPL 1-2/PM NRR/DORL/LPL 1-2/LAit*
*via email OFFICE NRR/DORLILPL 1-2/PM NRR/DORL/LPL 1-2/LAit*
NRR/DORLILPL 1-2/LA* NAME Jlamb KBeckford A Baxter DATE 1/17/2014 1/27/2014 1/28/2014 OFFICIAL RECORD COPY NRR/DORLILPL 1-2/BC MKhanna 1/29/2014}}
NRR/DORLILPL 1-2/LA* NAME Jlamb KBeckford A Baxter DATE 1/17/2014 1/27/2014 1/28/2014 OFFICIAL RECORD COPY NRR/DORLILPL 1-2/BC MKhanna 1/29/2014}}

Revision as of 18:31, 21 June 2019

Acceptance Letter Regarding End of Interval Relief Requests Associated with the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF3406 and MF3407)
ML14017A042
Person / Time
Site: Oyster Creek
Issue date: 01/29/2014
From: Meena Khanna
Plant Licensing Branch 1
To: Pacilio M
Exelon Nuclear
Lamb J
References
TAC MF3406, TAC MF3407
Download: ML14017A042 (3)
v • d • e


Text

Mr. Michael J. Pacilio UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 29, 2014 President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION -ACCEPTANCE LETTER REGARDING END OF INTERVAL RELIEF REQUESTS ASSOCIATED WITH THE FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NOS. MF3406 AND MF3407)

Dear Mr. Pacilio:

By letter dated January 7, 2014 (Agencywide Documents Access and Management System Accession No. ML14017A042), Exelon Generation Company, LLC submitted relief requests (RRs) from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components." These RRs apply to the fourth 1 0-year lnservice Inspection (lSI) interval, which concluded on January 14, 2013, for the Oyster Creek Nuclear Generating Station. The fourth 1 0-year lSI interval complied with the ASME B&PV Code,Section XI, 1995 Edition with 1996 Addenda. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of these RRs. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations, the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the M. Pacilio environment.

If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me at (301) 415-3100 or by email at John.Lamb@nrc.gov.

Docket No. 50-219 cc: Distribution via Listserv Sincerely, Meena Khanna, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation M. Pacilio environment.

If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me at (301) 415-3100 or by email at John. Lamb@nrc.gov.

Docket No. 50-219 cc: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsNrrLAABaxter Resource RidsNrrPMOysterCreek Resource RidsNrrDoriDpr Resource RidsNrrDeEeeb Resource RidsAcrsAcnw_MaiiCTR Resource Sincerely, Ira/ Meena Khanna, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNRRDorllpl1-2 Resource RidsNrrDirsltsb Resource RidsRgn1 MaiiCenter Resource LPLI-2 RIF ADAMS Accession No: ML14017A042

  • via email OFFICE NRR/DORLILPL 1-2/PM NRR/DORL/LPL 1-2/LAit*

NRR/DORLILPL 1-2/LA* NAME Jlamb KBeckford A Baxter DATE 1/17/2014 1/27/2014 1/28/2014 OFFICIAL RECORD COPY NRR/DORLILPL 1-2/BC MKhanna 1/29/2014

Retrieved from "https://kanterella.com/w/index.php?title=ML14017A042&oldid=1733338"