ML16243A489: Difference between revisions

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{{#Wiki_filter:Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 1, 2016 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 1, 2016 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555


==SUBJECT:==
==SUBJECT:==
DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: INSERVICE INSPECTION INTERVAL PROPOSED ALTERNATIVE (15R-08) (CAC NOS. MF8090 AND MF8091)  
DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3 -
ACCEPTANCE OF REQUESTED LICENSING ACTION RE: INSERVICE INSPECTION INTERVAL PROPOSED ALTERNATIVE (15R-08)
(CAC NOS. MF8090 AND MF8091)


==Dear Mr. Hanson:==
==Dear Mr. Hanson:==
By letter dated June 30, 2016 (RS-16-130) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16187A295), Exelon Generation Company, LLC (EGC, the licensee), submitted a proposed alternative for Dresden Nuclear Power Station (DNPS), Unit Nos. 2 and 3, that would allow DNPS to use an alternative to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code), Section XI, for the fifth 10-year inservice inspection (ISi) interval which began on January 20, 2013, and is currently scheduled to end on January 19, 2023. Included in the submittal EGC is requesting NRC approval for the remaining term of the DNPS, Unit Nos. 2 and 3, renewed facility operating licenses, currently expiring on December 22, 2029, and January 12, 2031, respectively.
 
By letter dated August 18, 2016 (ADAMS Accession No. ML16229A547), the NRC requested that EGC provide additional information in order for the NRC staff to complete its acceptance review. In response, EGC provided the NRC with supplemental letter dated August 22, 2016 (RS-16-166) (ADAMS Accession No. ML16236A251).
By letter dated June 30, 2016 (RS-16-130) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16187A295), Exelon Generation Company, LLC (EGC, the licensee), submitted a proposed alternative for Dresden Nuclear Power Station (DNPS), Unit Nos. 2 and 3, that would allow DNPS to use an alternative to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code), Section XI, for the fifth 10-year inservice inspection (ISi) interval which began on January 20, 2013, and is currently scheduled to end on January 19, 2023. Included in the submittal EGC is requesting NRC approval for the remaining term of the DNPS, Unit Nos. 2 and 3, renewed facility operating licenses, currently expiring on December 22, 2029, and January 12, 2031, respectively. By letter dated August 18, 2016 (ADAMS Accession No. ML16229A547), the NRC requested that EGC provide additional information in order for the NRC staff to complete its acceptance review. In response, EGC provided the NRC with supplemental letter dated August 22, 2016 (RS-16-166) (ADAMS Accession No. ML16236A251). The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the U.S. Nuclear Regulatory Commission (NRC) staff to complete its detailed technical review. The acceptance review is also intended to identify whether the submittal has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the U.S. Nuclear Regulatory Commission (NRC) staff to complete its detailed technical review. The acceptance review is also intended to identify whether the submittal has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Pursuant to Title 1 O of the Code of Federal Regulations (1 O CFR) 50.55a(z)(1  
Pursuant to Title 1O of the Code of Federal Regulations (1 O CFR) 50.55a(z)(1 ), EGC requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety.
), EGC requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety. The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete 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 environment.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete 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 environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate
Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate B. Hanson acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
 
B. Hanson                                       acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
If you have any questions, please contact me at (301) 415-1129.
If you have any questions, please contact me at (301) 415-1129.
Docket Nos. 50-237 and 50-249 cc: Distribution via ListServ Russell S. Haskell II, Project Manager Plant Licensing Branch 3-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation B. Hanson acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
Russell S. Haskell II, Project Manager Plant Licensing Branch 3-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237 and 50-249 cc: Distribution via ListServ
If you have any questions, please contact me at (301) 415-1129.
 
Docket Nos. 50-237 and 50-249 cc: Distribution via ListServ DISTRIBUTION:
ML16243A489 OFFICE       DORL/LPL3-2/PM       DORL/LPL3-2/LA     DORL/LPL3-2/BC         DORL/LPL3-2/PM NAME         RHaskell             SRohrer             GEMiller (JDion for) RHaskell DATE         08/31/16             08/31/16           09/01/16               09/01/16}}
PUBLIC LPL3-2 R/F RidsRgn3MailCenter Resource RidsAcrs_MailCTR Resource Sincerely, /RA/ Russell S. Haskell II, Project Manager Plant Licensing Branch 3-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDeEvib Resource RidsNrrDorllpl3-2 Resource RidsNrrLASRohrer Resource RidsNrrPMDresden Resource ADAMS Accession No. ML16243A489 OFFICE DORL/LPL3-2/PM DORL/LPL3-2/LA DORL/LPL3-2/BC DORL/LPL3-2/PM NAME RHaskell SRohrer GEMiller (JDion for) RHaskell DATE 08/31/16 08/31/16 09/01/16 09/01/16 OFFICIAL RECORD COPY}}

Revision as of 14:39, 30 October 2019

Acceptance of Requested Licensing Action Inservice Inspection Interval Proposed Alternative (I5R-08) (CAC Nos. MF8090 and MF8091)
ML16243A489
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 09/01/2016
From: Haskell R
Plant Licensing Branch III
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
Haskell R
References
CAC MF8090, CAC MF8091
Download: ML16243A489 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 1, 2016 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3 -

ACCEPTANCE OF REQUESTED LICENSING ACTION RE: INSERVICE INSPECTION INTERVAL PROPOSED ALTERNATIVE (15R-08)

(CAC NOS. MF8090 AND MF8091)

Dear Mr. Hanson:

By letter dated June 30, 2016 (RS-16-130) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16187A295), Exelon Generation Company, LLC (EGC, the licensee), submitted a proposed alternative for Dresden Nuclear Power Station (DNPS), Unit Nos. 2 and 3, that would allow DNPS to use an alternative to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code),Section XI, for the fifth 10-year inservice inspection (ISi) interval which began on January 20, 2013, and is currently scheduled to end on January 19, 2023. Included in the submittal EGC is requesting NRC approval for the remaining term of the DNPS, Unit Nos. 2 and 3, renewed facility operating licenses, currently expiring on December 22, 2029, and January 12, 2031, respectively. By letter dated August 18, 2016 (ADAMS Accession No. ML16229A547), the NRC requested that EGC provide additional information in order for the NRC staff to complete its acceptance review. In response, EGC provided the NRC with supplemental letter dated August 22, 2016 (RS-16-166) (ADAMS Accession No. ML16236A251). The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the U.S. Nuclear Regulatory Commission (NRC) staff to complete its detailed technical review. The acceptance review is also intended to identify whether the submittal has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Pursuant to Title 1O of the Code of Federal Regulations (1 O CFR) 50.55a(z)(1 ), EGC requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete 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 environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate

B. Hanson acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

If you have any questions, please contact me at (301) 415-1129.

Russell S. Haskell II, Project Manager Plant Licensing Branch 3-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237 and 50-249 cc: Distribution via ListServ

ML16243A489 OFFICE DORL/LPL3-2/PM DORL/LPL3-2/LA DORL/LPL3-2/BC DORL/LPL3-2/PM NAME RHaskell SRohrer GEMiller (JDion for) RHaskell DATE 08/31/16 08/31/16 09/01/16 09/01/16