|
|
| (6 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML12216A027 | | | number = ML12216A027 |
| | issue date = 08/03/2012 | | | issue date = 08/03/2012 |
| | title = Wolf Creek - Acceptance Review Email, Relief Request I3R-07 from ASME Code Case N-7229 for Examination of Reactor Vessel Head Penetration Welds, for Remainder of Third 10-Year Inservice Inspection Interval (TAC No. ME9078) | | | title = Acceptance Review Email, Relief Request I3R-07 from ASME Code Case N-7229 for Examination of Reactor Vessel Head Penetration Welds, for Remainder of Third 10-Year Inservice Inspection Interval |
| | author name = Beltz T A | | | author name = Beltz T |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Wideman S G | | | addressee name = Wideman S |
| | addressee affiliation = Wolf Creek Nuclear Operating Corp | | | addressee affiliation = Wolf Creek Nuclear Operating Corp |
| | docket = 05000482 | | | docket = 05000482 |
| | license number = NPF-042 | | | license number = NPF-042 |
| | contact person = Beltz T A | | | contact person = Beltz T |
| | case reference number = TAC ME9078, N-7229 | | | case reference number = TAC ME9078, N-7229 |
| | document type = E-Mail | | | document type = E-Mail |
| | page count = 1 | | | page count = 1 |
| | project = TAC:ME9078 | | | project = TAC:ME9078 |
| | stage = Other | | | stage = Acceptance Review |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:From:Beltz, TerryTo:Wideman Steve GCc:Tsao, John; Burkhardt, Janet; Chen, Qiao-Lynn; wimuile@WCNOC.comSubject:Wolf Creek Generating Station - Acceptance Review re: Relief Request I3R-07 (TAC No. ME9078)Date:Friday, August 03, 2012 7:07:41 AM Dear Mr. Wideman: | | {{#Wiki_filter:From: Beltz, Terry To: Wideman Steve G Cc: Tsao, John; Burkhardt, Janet; Chen, Qiao-Lynn; wimuile@WCNOC.com |
| By letter dated July 2, 2012, (ADAMS Accession No. ML12193A559), the Wolf CreekNuclear Operating Corporation (WCNOC) requested relief from certain requirements of theASME Code, Code Case N-729-1, as conditioned in 10 CFR 50.55a, for examination ofreactor vessel head penetration welds at the Wolf Creek Generating Station. | | |
| The purpose of this e-mail is to provide the final results of the NRC staff's acceptancereview of this request. The acceptance review was performed to determine if there issufficient technical information in scope and depth to allow the NRC staff to complete itsdetailed technical review and make an independent assessment regarding theacceptability of the proposed change. The acceptance review is also intended to identifywhether the application has any readily apparent information insufficiencies in itscharacterization of the regulatory requirements or the licensing basis of the plant. | | ==Subject:== |
| The NRC staff has reviewed your application and concluded that there appears to besufficient technical information, both in scope and depth, to enable the staff to proceedwith its detailed technical review and make an independent assessment regarding theacceptability of the LAR in terms of regulatory requirements and the protection of publichealth and safety and the environment. | | Wolf Creek Generating Station - Acceptance Review re: Relief Request I3R-07 (TAC No. ME9078) |
| If additional information is needed for the staff to complete its technical review, you will beadvised by separate correspondence. | | Date: Friday, August 03, 2012 7:07:41 AM |
| | |
| | ==Dear Mr. Wideman:== |
| | |
| | By letter dated July 2, 2012, (ADAMS Accession No. ML12193A559), the Wolf Creek Nuclear Operating Corporation (WCNOC) requested relief from certain requirements of the ASME Code, Code Case N-729-1, as conditioned in 10 CFR 50.55a, for examination of reactor vessel head penetration welds at the Wolf Creek Generating Station. |
| | The purpose of this e-mail is to provide the final results of the NRC staffs acceptance review of this request. 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 and make an independent assessment regarding the acceptability of the proposed change. 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. |
| | The NRC staff has reviewed your application and concluded that there appears to be sufficient technical information, both in scope and depth, to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the LAR in terms of regulatory requirements and the protection of public health and safety and the environment. |
| | If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. |
| Should you have any questions regarding this review, please contact me at (301) 415-3049. | | Should you have any questions regarding this review, please contact me at (301) 415-3049. |
| | | Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov}} |
| Sincerely, Terry A. Beltz, Senior Project ManagerPlant Licensing Branch III-1Division of Operating Reactor LicensingOffice of Nuclear Reactor Regulation (301) 415-3049Terry.Beltz@nrc.gov | |
| }} | |
Letter Sequence Acceptance Review |
|---|
|
|
MONTHYEARET 12-0010, 10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds2012-07-0202 July 2012
10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds
Project stage: Other
ML12216A0272012-08-0303 August 2012
Acceptance Review Email, Relief Request I3R-07 from ASME Code Case N-7229 for Examination of Reactor Vessel Head Penetration Welds, for Remainder of Third 10-Year Inservice Inspection Interval
Project stage: Acceptance Review
ML12248A0802012-09-0404 September 2012
Email, Request for Additional Information, Relief Request I3R-07 from ASME Code Case N-729-1 for Examination of Reactor Vessel Head Penetration Welds, for Remainder of Third 10-Year Inservice Inspection Interval
Project stage: RAI
ET 12-0024, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds2012-10-15015 October 2012
Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds
Project stage: Response to RAI
ML12353A2412013-01-0404 January 2013
Relief Request I3R-07 from ASME Code Case N-729-1 for Examination of Reactor Vessel Head Penetration Welds, for Remainder of Third 10-Year Inservice Inspection Interval
Project stage: Other
2012-08-03
[Table View] |
|
|---|
Category:E-Mail
MONTHYEARML24263A0832024-09-19019 September 2024
NRR E-mail Capture - Acceptance Review Wolf Creek Revision to Technical Specification to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions
ML24250A0252024-09-0606 September 2024
NRR E-mail Capture - Acceptance Review Wolf Creek Revision to Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology)
ML23360A1562023-12-26026 December 2023
NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise the Ventilation Filter Testing Program in Technical Specifications
ML23166A0622023-06-15015 June 2023
NRR E-mail Capture - Acceptance Review - Wolf Creek Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded post-tensioning System Components
ML23090A1042023-03-31031 March 2023
NRR E-mail Capture - Acceptance Review Wolf Creek Request for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications
ML23090A0072023-03-31031 March 2023
NRR E-mail Capture - Acceptance Review Wolf Creek Request for Relief for Follow-Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Peened Surface
ML23080A0652023-03-21021 March 2023
NRR E-mail Capture - Wolf Creek Generating Station Evacuation Time Estimate Analysis Review
ML23026A0222023-01-25025 January 2023
NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements
ML23009A4082023-01-0909 January 2023
NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise TS to Adopt Technical Specification Task Force (TSTF)-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections
ML22361A0052022-12-27027 December 2022
NRR E-mail Capture - Request for Additional Information Wolf Creek Request for Deviation from Fire Protection Program Requirements
ML22321A2662022-11-16016 November 2022
January 2023 Emergency Preparedness Program Inspection - Request for Information
ML22307A1372022-11-0202 November 2022
August 2022 Emergency Preparedness Exercise Inspection Unresolved Item - Request for Information
ML22251A1312022-09-0808 September 2022
NRR E-mail Capture - Acceptance Review - Wolf Creek Request for Deviation from Fire Protection Program Requirements to Allow Use of Portable Lighting
ML22215A2742022-08-0202 August 2022
Inservice Inspection Request for Information
ML22208A1322022-07-27027 July 2022
NRR E-mail Capture - Wolf Creek Table of Contents LAR
ML22166A3222022-06-14014 June 2022
August 2022 Emergency Preparedness Exercise Inspection - Request for Information
ML22131A0522022-05-11011 May 2022
NRR E-mail Capture - Draft Supplemental Information Needed for Acceptance - Wolf Creek Inservice Inspection Relief Request for Reactor Pressure Vessel Head Penetration Nozzles with Peened Surface
ML22055A1142022-02-23023 February 2022
NRR E-mail Capture - Request for Additional Information - Wolf Creek Request to Revise Diesel Generator Completion Time
ML22045A4512022-02-14014 February 2022
NRR E-mail Capture - Request for Additional Information - Wolf Creek Steam Generator Inspection Report 24th Refueling
ML22026A4392022-01-26026 January 2022
NRR E-mail Capture - Wolf Creek Acceptance Review Results - Removal of TS Table of Contents (L-2022-LLA-0008)
ML22025A3612022-01-21021 January 2022
PI&R RFI Final
ML21327A2602021-11-23023 November 2021
NRR E-mail Capture - Request for Additional Information - Wolf Creek Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
ML21309A0332021-11-0505 November 2021
NRR E-mail Capture - Acceptance Review - Wolf Creek Revision of Technical Specification 3.8.1, AC Sources - Operating
ML21307A4202021-11-0303 November 2021
NRR E-mail Capture - Acceptance Review - Wolf Creek Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
ML21271A1952021-09-28028 September 2021
E-mail 9-28-21 RFI for Wc EP Inspection Nov 2021
ML21259A0652021-09-16016 September 2021
NRR E-mail Capture - Draft Supplemental Information Needed for Acceptance - Wolf Creek License Amendment and Exemption Requests Regarding GSI-191 (EPIDs L-2021-LLA-0152 and L-2021-LLE-0039)
ML21221A1282021-08-0505 August 2021
NRR E-mail Capture - Urgent: Draft Request for Additional Information - Wolf Creek one-time Request for Exemption from the Biennial Emergency Preparedness Exercise
ML21189A0252021-07-0101 July 2021
NRR E-mail Capture - Acceptance Review - Wolf Creek Request Revision to the Emergency Plan Related to on-shift Staffing
ML21230A3922021-05-19019 May 2021
May 19, 2021 Dricks Response to Gurdziel Letter Dated May 13, 2021 - August 17, 2021
ML21102A3342021-04-12012 April 2021
Email 4-12-21 RFI for In-Office Rvw of Recent RERP and a Related EPIP Change
ML21064A0342021-03-0404 March 2021
NRR E-mail Capture - Wolf Creek Generating Station Upcoming Steam Generator Tube Inservice Inspection
ML20353A2712020-12-18018 December 2020
NRR E-mail Capture - Acceptance Review - Wolf Creek Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange
ML20349A3092020-12-14014 December 2020
NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request for Change to Owner Licensee Names
ML20297A3022020-10-22022 October 2020
NRR E-mail Capture - Acceptance Review - Wolf Creek Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
ML20262A7512020-09-17017 September 2020
NRR E-mail Capture - Requests for Additional Information: Wolf Creek Amendment Request to Modify Technical Specification Surveillance Frequency Consistent with TSTF-425
ML20191A0222020-07-0606 July 2020
NRR E-mail Capture - Acceptance Review - Wolf Creek Request in Support of Replacement Engineered Safety Features Transformers with Load Tap Changers
ML20162A1642020-06-0909 June 2020
Email June 9, 2020 - RFI in Preparation for Wolf Creek EP Program Inspection
ML20149K4272020-05-22022 May 2020
NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)
ML20133J8972020-05-12012 May 2020
12 May 2020 E-mail - RFI for NRC In-Office Inspection of Recent Wcngs Eplan_Eal Changes
ML20132A3442020-05-11011 May 2020
NRR E-mail Capture - Acceptance Review - Wolf Creek Generating Station License Amendment Request to Revise Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
ML20009E4802020-01-0909 January 2020
Relief Request to Utilize Code Case N-666-1 for Wolf Creek Generating Station - Request for Additional Information
ML19273A0232019-09-30030 September 2019
NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System,
ML19268B7172019-09-25025 September 2019
NRR E-mail Capture - Acceptance Review - Inservice Inspection (ISI) Program Relief Request to Use Code Case N-666-1
ML19261A2272019-09-18018 September 2019
NRR E-mail Capture - Regulatory Audit Plan - Wolf Creek Generating Station License Amendment Request to Revise Technical Specification 3.3.5
ML19255H3032019-09-12012 September 2019
NRR E-mail Capture - Acceptance Review - Relief Request I4R-07 to Utilize Code Case N-513-4
ML19224A5242019-08-12012 August 2019
NRR E-mail Capture - Request for Additional Information - License Amendment Request to Revise Wolf Creek Generating Station Technical Specification 3.3.5
ML19274D2752019-07-31031 July 2019
Request for Information-IR 05000482 2019-004, Dated 7/31/2019
ML19203A2362019-07-19019 July 2019
LTR-19-0291 Tom Gurdziel, E-mail July 18, 2019, Confirmatory Order on Wolf Creek
ML19112A1772019-04-22022 April 2019
NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation
ML19091A0362019-03-29029 March 2019
NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange
2024-09-06
[Table view] |
Text
From: Beltz, Terry To: Wideman Steve G Cc: Tsao, John; Burkhardt, Janet; Chen, Qiao-Lynn; wimuile@WCNOC.com
Subject:
Wolf Creek Generating Station - Acceptance Review re: Relief Request I3R-07 (TAC No. ME9078)
Date: Friday, August 03, 2012 7:07:41 AM
Dear Mr. Wideman:
By letter dated July 2, 2012, (ADAMS Accession No. ML12193A559), the Wolf Creek Nuclear Operating Corporation (WCNOC) requested relief from certain requirements of the ASME Code, Code Case N-729-1, as conditioned in 10 CFR 50.55a, for examination of reactor vessel head penetration welds at the Wolf Creek Generating Station.
The purpose of this e-mail is to provide the final results of the NRC staffs acceptance review of this request. 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 and make an independent assessment regarding the acceptability of the proposed change. 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.
The NRC staff has reviewed your application and concluded that there appears to be sufficient technical information, both in scope and depth, to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the LAR in terms of regulatory requirements and the protection of public health and safety and the environment.
If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
Should you have any questions regarding this review, please contact me at (301) 415-3049.
Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov
