ML11306A081: 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)
 
(3 intermediate revisions by the same user not shown)
Line 2: Line 2:
| number = ML11306A081
| number = ML11306A081
| issue date = 11/07/2011
| issue date = 11/07/2011
| title = Oconee Nuclear Station, Units 1, 2, & 3, Supplemental Information Needed for Acceptance of Requested Licensing Action Measurement Uncertainty Recapture Power Uprate License Amendment Request (TAC Nos. ME7164, ME7165, & ME7166)
| title = Supplemental Information Needed for Acceptance of Requested Licensing Action Measurement Uncertainty Recapture Power Uprate License Amendment Request (TAC Nos. ME7164, ME7165, & ME7166)
| author name = Stang J F
| author name = Stang J
| author affiliation = NRC/NRR/DORL/LPLII-1
| author affiliation = NRC/NRR/DORL/LPLII-1
| addressee name = Gillespie P
| addressee name = Gillespie P
Line 14: Line 14:
| page count = 5
| page count = 5
| project = TAC:ME7164, TAC:ME7165, TAC:ME7166
| project = TAC:ME7164, TAC:ME7165, TAC:ME7166
| stage = Supplement
| stage = Acceptance Review
}}
}}


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON.
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555*0001 November 7.2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672
D.C. 20555*0001 November 7.2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 OCONEE NUCLEAR STATION, UNITS 1, 2. AND 3 (OCONEE 1, 2, AND 3), SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NOS. ME7164, ME7165, AND ME7166)  
 
==SUBJECT:==
OCONEE NUCLEAR STATION, UNITS 1, 2. AND 3 (OCONEE 1, 2, AND 3),
SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NOS.
ME7164, ME7165, AND ME7166)


==Dear Mr. Gillespie:==
==Dear Mr. Gillespie:==


By letter dated September 20,2011, Duke Energy Carolinas, LLC (Duke, the licensee), submitted a license amendment request (LAR) for Oconee 1, 2, and 3. The proposed amendment requested approval of a measurement uncertainty recapture (MUR) power uprate. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. 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. Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, an amendment to the license (including the Technical Specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications.
By letter dated September 20,2011, Duke Energy Carolinas, LLC (Duke, the licensee), submitted a license amendment request (LAR) for Oconee 1, 2, and 3. The proposed amendment requested approval of a measurement uncertainty recapture (MUR) power uprate. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. 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.
Section 50.34 of 10 CFR addresses the content of technical information required.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, an amendment to the license (including the Technical Specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that the following information delineated in the enclosure to this letter is necessary to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed amendment request 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 the following information delineated in the enclosure to this letter is necessary to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.
P. Gillespie  
 
-In order to make the application complete, the NRC staff requests that Duke supplement the application to address the information requested in the enclosure 15 days after receipt of this letter. This will enable the NRC staff to complete its detailed technical review. If the response to the NRC staff's request is not received 15 days after receipt of this letter, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the application.
P. Gillespie                                     - 2 In order to make the application complete, the NRC staff requests that Duke supplement the application to address the information requested in the enclosure 15 days after receipt of this letter. This will enable the NRC staff to complete its detailed technical review. If the response to the NRC staff's request is not received 15 days after receipt of this letter, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
The information requested and associated time frame in this letter was discussed with Kent Alter of your staff on November 2, 2011.
The information requested and associated time frame in this letter was discussed with Kent Alter of your staff on November 2, 2011. If you have any questions, please contact me at (301) 415-1345 or via email John. Stang@nrc.gov.
If you have any questions, please contact me at (301) 415-1345 or via email John. Stang@nrc.gov.
Sincerely, hn Stang, Seni I nt Licensing Branch 11-1 Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287  
Sincerely, hn Stang, Seni Project Manager I nt Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287


==Enclosure:==
==Enclosure:==
As stated cc w/encl: Distribution via Listserv


As stated cc w/encl: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 OFFICE OF NUCLEAR REACTOR REGULATION ACCEPTANCE REVI EW -UNACCEPTABLE WITH OPPORTUNITY TO SUPPLEMENT LICENSE AMENDMENT REQUEST MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287 By application dated September 20,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 11269A 127), Duke Energy Carolinas, LLC (Duke, the licensee), requested approval of a measurement uncertainty recapture (MUR) power uprate and changes to the License and Technical Specifications (TSs) for the Oconee Nuclear Station, Units 1, 2, and 3 (Oconee 1, 2, and 3). The acceptance review is performed to determine if there is sufficient technical information in scope and depth to allow the Nuclear Regulatory Commission (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 units. The acceptance review has a lesser scope as compared to the detailed technical review. The issues described below were identified during the lesser scope of the acceptance review. The NRC staff requests a supplement to the September 20, 2011, application, 15 days after receipt of this letter. Address the following information:
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 OFFICE OF NUCLEAR REACTOR REGULATION ACCEPTANCE REVI EW - UNACCEPTABLE WITH OPPORTUNITY TO SUPPLEMENT LICENSE AMENDMENT REQUEST MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287 By application dated September 20,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11269A127), Duke Energy Carolinas, LLC (Duke, the licensee), requested approval of a measurement uncertainty recapture (MUR) power uprate and changes to the License and Technical Specifications (TSs) for the Oconee Nuclear Station, Units 1, 2, and 3 (Oconee 1, 2, and 3).
In Section 4 of the application other license amendment requests (LARs) are referenced.
The acceptance review is performed to determine if there is sufficient technical information in scope and depth to allow the Nuclear Regulatory Commission (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 units. The acceptance review has a lesser scope as compared to the detailed technical review. The issues described below were identified during the lesser scope of the acceptance review. The NRC staff requests a supplement to the September 20, 2011, application, 15 days after receipt of this letter.
It is not clear in the MUR application if it is dependent on the approval of the LARs or if the application is a stand-alone document.
Address the following information:
In addition, in the MUR application it was not clear if the current licensing basis was used or a future licensing basis based on NRC review and approval was used. Please make clear the relationship of the MUR LAR with all other LARs currently under review by the NRC, and any future LAR applications.
In Section 4 of the application other license amendment requests (LARs) are referenced. It is not clear in the MUR application if it is dependent on the approval of the LARs or if the application is a stand-alone document. In addition, in the MUR application it was not clear if the current licensing basis was used or a future licensing basis based on NRC review and approval was used. Please make clear the relationship of the MUR LAR with all other LARs currently under review by the NRC, and any future LAR applications. The NRC will not accept for review the MUR until all prerequisite LARs have been reviewed and approved by the NRC.
The NRC will not accept for review the MUR until all prerequisite LARs have been reviewed and approved by the NRC. In the MUR application it stated that an analysis is not bounded for the MUR uprate conditions that relate to a double steam line break. The LAR states that the analysis performed to date is preliminary and not final. Furthermore, it is only expected, but not confirmed, that the MUR conditions analyzed will provide acceptable results. Please provide assurance that all analysis and calculations that support the MUR power uprate have been completed, and are bounding for the MUR uprate conditions.
In the MUR application it stated that an analysis is not bounded for the MUR uprate conditions that relate to a double steam line break. The LAR states that the analysis performed to date is preliminary and not final. Furthermore, it is only expected, but not confirmed, that the MUR conditions analyzed will provide acceptable results. Please provide assurance that all analysis and calculations that support the MUR power uprate have been completed, and are bounding for the MUR uprate conditions.
Enclosure
Enclosure
-2 In the MUR power uprate application it stated that the impact of the Oconee 1, 2, and 3 reactor internals inspection plan had been evaluated.
 
The evaluation addressed the impact of MUR uprate on aging degradation in reactor internals.
                                              -2 In the MUR power uprate application it stated that the impact of the Oconee 1, 2, and 3 reactor internals inspection plan had been evaluated. The evaluation addressed the impact of MUR uprate on aging degradation in reactor internals. The MUR LAR referenced MRP-227-Revision 0, "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines," which provides generic inspection and evaluation guidelines based on a broad set of assumptions about plant operation. The Oconee 1, 2, and 3 reactor internals inspection plan (ANP-2951 , Revision 1) was developed in accordance with the generic requirements in MRP-227, Revision O. By letter dated November 8,2010 (ADAMS Accession No. ML103140599), the licensee submitted an LAR requesting NRC review and approval of the reactor vessel internals inspection program. The inspection plan referenced MRP-227, Revision O. However, by letter dated September 1, 2011 (ADAMS Accession No. ML11251A160), the licensee stated that the November 8, 2010, LAR would be updated to incorporate changes associated with NRC staff's review and approval of MRP-227, Revision O. The MUR LAR did not take into account the NRC staff's review and approval of MRP-227, and any changes to the reactor internals inspection plan as a result. As indicated above, please review the MUR power uprate application to assure that the LAR associated with the approval of the reactor vessel internals inspection plan is not a prerequisite LAR for the MUR power uprate. In addition, please verify that any changes that will be made to the November 8, 2010, LAR will not have any effect on the MUR power uprate.
The MUR LAR referenced MRP-227-Revision 0, "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines," which provides generic inspection and evaluation guidelines based on a broad set of assumptions about plant operation.
 
The Oconee 1, 2, and 3 reactor internals inspection plan (ANP-2951 , Revision 1) was developed in accordance with the generic requirements in MRP-227, Revision O. By letter dated November 8,2010 (ADAMS Accession No. ML 103140599), the licensee submitted an LAR requesting NRC review and approval of the reactor vessel internals inspection program. The inspection plan referenced MRP-227, Revision O. However, by letter dated September 1, 2011 (ADAMS Accession No. ML 11251A 160), the licensee stated that the November 8, 2010, LAR would be updated to incorporate changes associated with NRC staff's review and approval of MRP-227, Revision O. The MUR LAR did not take into account the NRC staff's review and approval of MRP-227, and any changes to the reactor internals inspection plan as a result. As indicated above, please review the MUR power uprate application to assure that the LAR associated with the approval of the reactor vessel internals inspection plan is not a prerequisite LAR for the MUR power uprate. In addition, please verify that any changes that will be made to the November 8, 2010, LAR will not have any effect on the MUR power uprate.
P. Gillespie                                         -2 In order to make the application complete, the NRC staff requests that Duke supplement the application to address the information requested in the enclosure 15 days after receipt of this letter. This will enable the NRC staff to complete its detailed technical review. If the response to the NRC staff's request is not received 15 days after receipt of this letter, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.                                               .
P. Gillespie -2 In order to make the application complete, the NRC staff requests that Duke supplement the application to address the information requested in the enclosure 15 days after receipt of this letter. This will enable the NRC staff to complete its detailed technical review. If the response to the NRC staff's request is not received 15 days after receipt of this letter, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the application.
The information requested and associated time frame in this letter was discussed with Kent Alter of your staff on November 2, 2011.
If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. . The information requested and associated time frame in this letter was discussed with Kent Alter of your staff on November 2, 2011. If you have any questions, please contact me at (301) 415-1345 or via email John .Stang@nrc.gov.
If you have any questions, please contact me at (301) 415-1345 or via email John .Stang@nrc.gov.
Sincerely, IRA! John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287  
Sincerely, IRA!
John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287


==Enclosure:==
==Enclosure:==
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLlI-1 RlF RidsAcrsAcnw_MailCtr Resource RidsNrrDirsltsb Resource RidsNrrDorlDpr Resource RidsNrrDorlLp2-1 Resource RidsNrrEmcb Resource RidsOgcRp Resource RidsNrrLAMOBrien Resource (hard copy) RidsRgn2MailCenter Resource RidsNrrPMOconeeResource (hard copy) JUribe, NRR *concurrence submitted b email dated NRRlLPL2-1/LA DE/EMCB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM MO'Brien MMurphy' GKulesa JStang 11/2111 1112/11 11f7111 11f7111 OFFICIAL RECORD COPY}}
PUBLIC                         LPLlI-1 RlF                           RidsAcrsAcnw_MailCtr Resource RidsNrrDirsltsb Resource       RidsNrrDorlDpr Resource               RidsNrrDorlLp2-1 Resource RidsNrrEmcb Resource           RidsOgcRp Resource                   RidsNrrLAMOBrien Resource (hard copy)
RidsRgn2MailCenter Resource   RidsNrrPMOconeeResource (hard copy)
JUribe, NRR
                                                                    *concurrence submitted b email dated NRRlLPL2-1/LA   DE/EMCB/BC           NRRlLPL2-1/BC   NRRlLPL2-1/PM MO'Brien         MMurphy'             GKulesa         JStang 11/2111           1112/11             11f7111         11f7111 OFFICIAL RECORD COPY}}

Latest revision as of 12:35, 12 November 2019

Supplemental Information Needed for Acceptance of Requested Licensing Action Measurement Uncertainty Recapture Power Uprate License Amendment Request (TAC Nos. ME7164, ME7165, & ME7166)
ML11306A081
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 11/07/2011
From: Stang J
Plant Licensing Branch II
To: Gillespie P
Duke Energy Carolinas
References
TAC ME7164, TAC ME7165, TAC ME7166
Download: ML11306A081 (5)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555*0001 November 7.2011 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2. AND 3 (OCONEE 1, 2, AND 3),

SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NOS.

ME7164, ME7165, AND ME7166)

Dear Mr. Gillespie:

By letter dated September 20,2011, Duke Energy Carolinas, LLC (Duke, the licensee), submitted a license amendment request (LAR) for Oconee 1, 2, and 3. The proposed amendment requested approval of a measurement uncertainty recapture (MUR) power uprate. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. 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.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, an amendment to the license (including the Technical Specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.

This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The NRC staff has reviewed your application and concluded that the following information delineated in the enclosure to this letter is necessary to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.

P. Gillespie - 2 In order to make the application complete, the NRC staff requests that Duke supplement the application to address the information requested in the enclosure 15 days after receipt of this letter. This will enable the NRC staff to complete its detailed technical review. If the response to the NRC staff's request is not received 15 days after receipt of this letter, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

The information requested and associated time frame in this letter was discussed with Kent Alter of your staff on November 2, 2011.

If you have any questions, please contact me at (301) 415-1345 or via email John. Stang@nrc.gov.

Sincerely, hn Stang, Seni Project Manager I nt Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287

Enclosure:

As stated cc w/encl: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 OFFICE OF NUCLEAR REACTOR REGULATION ACCEPTANCE REVI EW - UNACCEPTABLE WITH OPPORTUNITY TO SUPPLEMENT LICENSE AMENDMENT REQUEST MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287 By application dated September 20,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11269A127), Duke Energy Carolinas, LLC (Duke, the licensee), requested approval of a measurement uncertainty recapture (MUR) power uprate and changes to the License and Technical Specifications (TSs) for the Oconee Nuclear Station, Units 1, 2, and 3 (Oconee 1, 2, and 3).

The acceptance review is performed to determine if there is sufficient technical information in scope and depth to allow the Nuclear Regulatory Commission (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 units. The acceptance review has a lesser scope as compared to the detailed technical review. The issues described below were identified during the lesser scope of the acceptance review. The NRC staff requests a supplement to the September 20, 2011, application, 15 days after receipt of this letter.

Address the following information:

In Section 4 of the application other license amendment requests (LARs) are referenced. It is not clear in the MUR application if it is dependent on the approval of the LARs or if the application is a stand-alone document. In addition, in the MUR application it was not clear if the current licensing basis was used or a future licensing basis based on NRC review and approval was used. Please make clear the relationship of the MUR LAR with all other LARs currently under review by the NRC, and any future LAR applications. The NRC will not accept for review the MUR until all prerequisite LARs have been reviewed and approved by the NRC.

In the MUR application it stated that an analysis is not bounded for the MUR uprate conditions that relate to a double steam line break. The LAR states that the analysis performed to date is preliminary and not final. Furthermore, it is only expected, but not confirmed, that the MUR conditions analyzed will provide acceptable results. Please provide assurance that all analysis and calculations that support the MUR power uprate have been completed, and are bounding for the MUR uprate conditions.

Enclosure

-2 In the MUR power uprate application it stated that the impact of the Oconee 1, 2, and 3 reactor internals inspection plan had been evaluated. The evaluation addressed the impact of MUR uprate on aging degradation in reactor internals. The MUR LAR referenced MRP-227-Revision 0, "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines," which provides generic inspection and evaluation guidelines based on a broad set of assumptions about plant operation. The Oconee 1, 2, and 3 reactor internals inspection plan (ANP-2951 , Revision 1) was developed in accordance with the generic requirements in MRP-227, Revision O. By letter dated November 8,2010 (ADAMS Accession No. ML103140599), the licensee submitted an LAR requesting NRC review and approval of the reactor vessel internals inspection program. The inspection plan referenced MRP-227, Revision O. However, by letter dated September 1, 2011 (ADAMS Accession No. ML11251A160), the licensee stated that the November 8, 2010, LAR would be updated to incorporate changes associated with NRC staff's review and approval of MRP-227, Revision O. The MUR LAR did not take into account the NRC staff's review and approval of MRP-227, and any changes to the reactor internals inspection plan as a result. As indicated above, please review the MUR power uprate application to assure that the LAR associated with the approval of the reactor vessel internals inspection plan is not a prerequisite LAR for the MUR power uprate. In addition, please verify that any changes that will be made to the November 8, 2010, LAR will not have any effect on the MUR power uprate.

P. Gillespie -2 In order to make the application complete, the NRC staff requests that Duke supplement the application to address the information requested in the enclosure 15 days after receipt of this letter. This will enable the NRC staff to complete its detailed technical review. If the response to the NRC staff's request is not received 15 days after receipt of this letter, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. .

The information requested and associated time frame in this letter was discussed with Kent Alter of your staff on November 2, 2011.

If you have any questions, please contact me at (301) 415-1345 or via email John .Stang@nrc.gov.

Sincerely, IRA!

John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPLlI-1 RlF RidsAcrsAcnw_MailCtr Resource RidsNrrDirsltsb Resource RidsNrrDorlDpr Resource RidsNrrDorlLp2-1 Resource RidsNrrEmcb Resource RidsOgcRp Resource RidsNrrLAMOBrien Resource (hard copy)

RidsRgn2MailCenter Resource RidsNrrPMOconeeResource (hard copy)

JUribe, NRR

  • concurrence submitted b email dated NRRlLPL2-1/LA DE/EMCB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM MO'Brien MMurphy' GKulesa JStang 11/2111 1112/11 11f7111 11f7111 OFFICIAL RECORD COPY
Retrieved from "https://kanterella.com/w/index.php?title=ML11306A081&oldid=2110469"