ML12180A588: Difference between revisions
From kanterella
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 14: | Line 14: | ||
| page count = 8 | | page count = 8 | ||
| project = TAC:ME8157 | | project = TAC:ME8157 | ||
| stage = | |||
}} | }} | ||
Revision as of 14:25, 30 March 2018
Letter Sequence Other | |
|---|---|
TAC:ME8157, (Open) | |
MONTHYEARL-MT-12-050, Supplement to 10 CFR 50.55a Requests Associated with the Fifth Inservice Inspection Ten-Year Interval2012-05-16016 May 2012
[Table View]Supplement to 10 CFR 50.55a Requests Associated with the Fifth Inservice Inspection Ten-Year Interval Project stage: Supplement ML12139A0882012-05-18018 May 2012 Found Relief Request RR-007 Acceptable for Review Per NRR Office Instruction LIC-109 Project stage: Other ML12180A5882012-07-12012 July 2012 Approval of ISI Relief Request RR-007 for the Fifth 10-year Interval Project stage: Other 2012-05-18 |
| ML12180A588 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/12/2012 |
| From: | Istvan Frankl Plant Licensing Branch III |
| To: | Schimmel M A Northern States Power Co |
| Tam P S | |
| References | |
| TAC ME8157 | |
| Download: ML12180A588 (8) | |
Similar Documents at Monticello | |
|---|---|
Category:Letter
MONTHYEARML24318C5002024-11-19019 November 2024
[Table view]Letter to Robert Blanchard Tribal Chairman Bad River Band of Lake Superior Chippewa Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5172024-11-18018 November 2024 Letter to Robert Larsen President Lower Sioux Indian Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5232024-11-18018 November 2024 Letter to Alonzo Denney Chairman Santee Sioux Nation Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5252024-11-18018 November 2024 Letter to J Garrett Renville Tribal Chairman Sisseton Wahpeton Oyate of the Lake Traversee Re NOA Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5042024-11-18018 November 2024 Letter to Jeffrey Stiffarm President Fort Belknap Indian Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5322024-11-18018 November 2024 Letter to Robert Vanzile Jr Chairman Sokaogon Chippewa Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24312A1732024-11-18018 November 2024 Ltr. to Shawn Hafen, Site Vice President, Monticello Nuclear Generating Plant, Re., NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5152024-11-18018 November 2024 Letter to Faron Jackson Sr Chairman Leech Lake Band of Ojibwe Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5262024-11-18018 November 2024 Letter to Lonna Johnson Street Chairperson Spirit Lake Nation Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5302024-11-18018 November 2024 Letter to Michael Fairbanks Chairman White Earth Nation Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5272024-11-18018 November 2024 Letter to Thomas Fowler Chairman St. Croix Chippewa of Wisconsin Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5112024-11-18018 November 2024 Letter to John Johnson President Lac Du Flambeau Band of Lake Superior Chippewa Indians Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24312A3462024-11-18018 November 2024 Letter to Jaime Loichinger Director Office of Federal Agency Programs, Achp NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5202024-11-18018 November 2024 Letter to Grant Johnson President Prairie Island Indian Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5182024-11-18018 November 2024 Letter to Gena Kakkak Chairwoman Menominee Indian Tribe of Wisconsin Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5062024-11-18018 November 2024 Letter to Robert Deschampe Tribal Chair Grand Portage Band of Lake Superior Chippewa Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24312A3202024-11-18018 November 2024 Letter to Durell Cooper Tribal Chairman Apache Tribe of Oklahoma Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5032024-11-18018 November 2024 Letter to Anthony Reider President Flandreau Santee Sioux Tribe NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24312A3512024-11-18018 November 2024 Letter to Amy Spong, Deputy State Historic Preservation Officer, Re., NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5012024-11-18018 November 2024 Letter to Catherine Chavers Tribal Chairwoman Bois Forte Band Chippewa Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5162024-11-18018 November 2024 Letter to James Williams Jr Chairman Lac Vieux Desert Band of Lake Superior Chippewa Indians Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5242024-11-18018 November 2024 Letter to Cole Miller Chairman Shakopee Mdewakaton Sioux Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5312024-11-18018 November 2024 Letter to Virgil Wind Chief Executive Mille Lacs Band of Ojibwe Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5222024-11-18018 November 2024 Letter to Darrell Seki Chairman Red Lake Nation Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5052024-11-18018 November 2024 Letter to Bruce Savage Tribal Chairperson Found Du Lac Band of Lake Superior Chippewa Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5022024-11-18018 November 2024 Letter to Reggie Wassana Governor Cheyenne and Arapaho Tribes NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5212024-11-18018 November 2024 Letter to Nicole Boyd Chairwoman Red Cliff Band of Lake Superior Chippewa Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5282024-11-18018 November 2024 Letter to Jamie Azure Chairman Turtle Mountain Band of Chippewa Indians Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5092024-11-18018 November 2024 Letter to Doreen Blaker President Keweenaw Bay Indian Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5102024-11-18018 November 2024 Letter to Louis Taylor Chairman Lac Courte Oreilles Band of Lake Superior Chippewa Indians Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR ML24318C5192024-11-18018 November 2024 Letter to Michael Laroque President Minnesota Chippewa Tribe Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5292024-11-18018 November 2024 Letter to Kevin Jensvold Tribal Chairman Upper Sioux Community Re NOA of the Final EIS for the Monticello Nuclear Generating Plant, Unit 1 SLR ML24318C5072024-11-18018 November 2024 Letter Timothy Rhodd Chairman Iowa Tribe of Kansas and Nebraska Re NOA of the Final EIS for the Monticello Nuclear Generating Plant Unit 1 SLR IR 05000263/20240032024-11-13013 November 2024 Integrated Inspection Report 05000263/2024003 ML24283A1192024-10-28028 October 2024 Letter to Shawn Hafen, Re Monticello Subsequent License Renewal Schedule Change L-MT-24-038, Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI2024-10-15015 October 2024 Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI ML24277A0202024-10-0303 October 2024 Operator Licensing Examination Approval Monticello Nuclear Generating Plant, October 2024 ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 IR 05000263/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000263/2024011 L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2024-09-26026 September 2024 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements L-MT-24-029, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI2024-09-13013 September 2024 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI IR 05000263/20240052024-08-30030 August 2024 Updated Inspection Plan and Follow-Up Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2024005) L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves IR 05000263/20244202024-08-21021 August 2024 Security Baseline Inspection Report 05000263/2024420 - Cover Letter IR 05000263/20240022024-08-14014 August 2024 Integrated Inspection Report 05000263/2024002 ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24215A2992024-07-23023 July 2024 Minnesota State Historic Preservation Office Comments on Monticello SLR Draft EIS 2024-09-26 Category:Safety Evaluation MONTHYEARML24199A1752024-10-0101 October 2024
[Table view]Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves ML24138A1212024-07-0202 July 2024 Alternative Request RR-002 ML24077A0012024-03-18018 March 2024 Safety Evaluation to the SLRA of Monticello Nuclear Generating Plant, Unit 1 ML23248A2092023-09-18018 September 2023 – Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation Valve ML23107A2852023-04-25025 April 2023 Authorization and Safety Evaluation for Alternative Request PR-08 ML23079A0742023-04-11011 April 2023 Request RR-003 to Use Later Edition of ASME Section XI Code for ISI Code of Record ML22357A1002023-03-31031 March 2023 And Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML23012A1562023-01-13013 January 2023 Issuance of Amendment No. 210 Re Revised Methodologies for Determining the Core Operating Limits (EPID L-2021-LLA-0144) - Non-proprietary ML22318A2152022-12-27027 December 2022 Issuance of Amendment No. 209 Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank ML22264A1062022-10-31031 October 2022 Issuance of Amendment No. 208 Residual Heat Removal Drywell Spray Header and Nozzle Surveillance Frequency ML22270A2312022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request No. VR-10 ML22154A5502022-06-0707 June 2022 Authorization and Safety Evaluation for Alternative Request No. PR-02 ML22126A1342022-05-12012 May 2022 Authorization and Safety Evaluation for Alternative Request No. PR-05 ML22098A1272022-05-0202 May 2022 Authorization and Safety Evaluation for Alternative Request No. VR-02 ML22018A1772022-01-21021 January 2022 Authorization and Safety Evaluation for Alternative Request No. VR-05 ML21223A2802021-10-15015 October 2021 Issuance of Amendment No. 207 Adoption of TSTF-564 Safety Limit MCPR ML21148A2742021-07-12012 July 2021 Issuance of Amendment No. 206 TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20352A3492021-01-0808 January 2021 Issuance of Amendment No. 205, Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-582, RPV WIC Enhancements, and TSTF-583-T, TSTF-582 Diesel Generator Variation ML20346A0972020-12-21021 December 2020 Request for Alternative for Examination of Reactor Pressure Vessel Threads in Flange ML20336A1602020-12-0909 December 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20307A0172020-11-0202 November 2020 Request for Alternative for Core Support Structure Weld Examination ML20210M0142020-09-0808 September 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20174A5452020-07-15015 July 2020 Request for Alternative for Pressure Isolation Valve Testing ML20153A4012020-06-0101 June 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML20135G9922020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML20134H9582020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML19255F5822019-10-0101 October 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4376; EPID No. L-2014-JLD-0052) ML19162A0932019-07-30030 July 2019 Issuance of Amendment No, 202 Regarding Deletion of the Note Associated with Technical Specification 3.5.1., Erccs - Operating ML19074A2692019-04-22022 April 2019 Non-Proprietary - Issuance of Amendment Revision to Technical Specifications 2.1.2 Safety Limit Minimum Critical Power Ratio ML19052A1422019-03-11011 March 2019 Correction to License Amendment No. 198 Related to Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML19065A2002019-03-11011 March 2019 Correction to License Amendment No. 200 Related to Adoption of TSTF-425, Relocated Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19007A0902019-01-28028 January 2019 Issuance of Amendment Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5B ML18291B2142018-11-26026 November 2018 Issuance of Amendment Adoption of TSTF-551 Revise Secondary Containment Surveillance Requirements ML18250A0752018-10-29029 October 2018 Issuance of Amendment Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18270A0152018-10-19019 October 2018 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM Code ML17345A0462018-03-0606 March 2018 Issuance of Amendment No. 197 to Adopt Changes to the Emergency Plan (CAC No. MF9560; EPID L-2017-LLA-0184) ML17319A5912017-12-10010 December 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17310B2392017-11-28028 November 2017 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Unit Staff Qualifications (CAC Nos. MF9545, MF9546, and MF9547; EPID L-2017-LLA-0195) ML17123A3212017-06-16016 June 2017 Issuance of Amendment Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing ML17122A1572017-05-15015 May 2017 Request for Alternative to Use Code Case OMN-20 for the Fifth 10-Year Inservice Testing Interval ML17103A2352017-04-25025 April 2017 Issuance of Amendment Technical Specification 5.5.11 Primary Containment Leakage Rate Testing Program ML17013A4352017-02-27027 February 2017 Issuance of Amendment Revision to Technical Specification Surveillance Requirement 3.8.4.2 ML17054C3942017-02-23023 February 2017 Non-Proprietary Issuance of Amendment Extended Flow Window ML16320A0212016-11-28028 November 2016 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Review of Changes to the Northern States Power Company Quality Assurance Topical Report ML16244A1202016-09-0606 September 2016 Generation Plant - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Vents) ML16208A4622016-08-0303 August 2016 Safety Evaluation for Request for Alternative Associated with Reactor Pressure Vessel Internals and Components Inspection for the Fifth 10-Year Interval ML16196A3032016-08-0101 August 2016 Issuance of Amendment Technical Specifications Surveillance Requirement 3.5.1.3 B to Correct Alternative Nitrogen System Pressure (Cac. No. MF6704) ML16125A1652016-06-21021 June 2016 Issuance of Amendment Technical Specifications Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-523, Revision 2 Generic Letter 2008-01, Managing Gas Accumulation 2024-08-27 Category:Code Relief or Alternative MONTHYEARML24222A1822024-08-27027 August 2024
[Table view]– Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves ML23248A2092023-09-18018 September 2023 – Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation Valve ML23123A4222023-05-16016 May 2023 – Request RR 001 to Use Later Edition of ASME BPV Section XI Code for Cisi Program ML23107A2852023-04-25025 April 2023 Authorization and Safety Evaluation for Alternative Request PR-08 ML23017A2222023-01-13013 January 2023 Verbal Authorization of Proposed Alternative PR-08 Regarding Inservice Testing Requirements of Certain High Pressure Coolant Injection System Components (EPID L-2022-LLR-0088) (Email) ML22314A2162022-11-16016 November 2022 Withdrawal of Alternative Request VR-08 ML22270A2312022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request No. VR-10 ML22208A1952022-08-0303 August 2022 Summary of July 26, 2022, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Alternative Request for Excess Flow Check Valves at Monticello Nuclear Generating Plant ML22126A1052022-06-21021 June 2022 Authorization and Safety Evaluation for Alternative Request No. VR-01 ML22154A5502022-06-0707 June 2022 Authorization and Safety Evaluation for Alternative Request No. PR-02 ML22126A1342022-05-12012 May 2022 Authorization and Safety Evaluation for Alternative Request No. PR-05 ML22130A6562022-05-11011 May 2022 Authorization and Safety Evaluation for Alternative Request No. PR-04 ML22098A1272022-05-0202 May 2022 Authorization and Safety Evaluation for Alternative Request No. VR-02 ML22110A1232022-04-25025 April 2022 Withdrawal of Relief Requests PR-09 and VR-07 (Epids: L 2021 Llr 0095 and L 2022 Llr 0021) ML22018A1772022-01-21021 January 2022 Authorization and Safety Evaluation for Alternative Request No. VR-05 ML20307A0172020-11-0202 November 2020 Request for Alternative for Core Support Structure Weld Examination ML20174A5452020-07-15015 July 2020 Request for Alternative for Pressure Isolation Valve Testing ML20135G9922020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML18270A0152018-10-19019 October 2018 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM Code L-MT-18-023, 10 CFR 50.55a Request RR-012: Inservice Inspection Impracticality in Accordance with 10 CFR 50 .55a(g)(5)(iii) During the Fifth Ten-Year Interval2018-05-11011 May 2018 10 CFR 50.55a Request RR-012: Inservice Inspection Impracticality in Accordance with 10 CFR 50 .55a(g)(5)(iii) During the Fifth Ten-Year Interval ML17122A1572017-05-15015 May 2017 Request for Alternative to Use Code Case OMN-20 for the Fifth 10-Year Inservice Testing Interval ML16208A4622016-08-0303 August 2016 Safety Evaluation for Request for Alternative Associated with Reactor Pressure Vessel Internals and Components Inspection for the Fifth 10-Year Interval L-MT-15-083, 10 CFR 50.55a Request No. RR-010: Request for Approval of an Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection2015-11-20020 November 2015 10 CFR 50.55a Request No. RR-010: Request for Approval of an Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection ML15028A1522015-02-19019 February 2015 Relief Request RR-009 Regarding Relief from Examination Coverage Requirements of Section XI of the ASME Code for the Fifth 10-Year Inservice Inspection Program Interval ML15013A0362015-01-23023 January 2015 Relief Request RR-008 Alternative to ASME Code, Section XI, Examination Requirements for the Reactor Pressure Vessel Shroud Support Plate Welds H8 and H9 for the Fifth 10-Year ISI Interval ML14223A5812014-08-27027 August 2014 Alternative Request Vr 05 to the Testing Requirements of the ASME OM Code for the Fifth 10-Year Inservice Inspection Program Interval ML12244A2722012-09-26026 September 2012 Relief from the Requirements of ASME OM Code for the Fifth Ten-Year IST Program Interval (TAC Nos. ME8067, ME8088 Through ME8096) ML12180A5882012-07-12012 July 2012 Approval of ISI Relief Request RR-007 for the Fifth 10-year Interval ML1020006722010-07-28028 July 2010 Approval of Alternative to Use ASME Code Case N-705 to Address Cracks at the Standby Liquid Control Tank L-MT-10-014, Request 10 CFR 50.55a Request 17: Extension of Permanent Relief from Volumetric Examination of Reactor Pressure Vessel Circumferential Shell Welds for the Renewed Operating License Term2010-03-12012 March 2010 Request 10 CFR 50.55a Request 17: Extension of Permanent Relief from Volumetric Examination of Reactor Pressure Vessel Circumferential Shell Welds for the Renewed Operating License Term ML0617103642006-07-0303 July 2006 Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 - Use of ASME Code Case N-513-2 L-MT-05-074, Request to Use Subsequent Edition and Addenda of ASME Code for Inservice Testing2005-07-29029 July 2005 Request to Use Subsequent Edition and Addenda of ASME Code for Inservice Testing ML0505600492005-03-0808 March 2005 Fourth 10-Year Inservice Inspection Interval Request for Relief to Use Code Case N-661 ML0436300192005-01-0606 January 2005 Relief, Fourth 10-year Inservice Inspection Interval Request for Relief No. 4, MC2222 ML0407004152004-03-25025 March 2004 Third 10-Year Interval Inservice Inspection Request for Relief RR-17, Involving Repair/Replacement Activity on the Topworks of Main Steam Safety Relief Valve (SRV) G ML0401607382004-02-26026 February 2004 Prairie, Units 1 and 2, Kewaunee, Point Beach, Units 1 and 2, Palisades, Re Request for Alternatives to ASME Section XI, Appendix Viii, Supplement 10 ML0320401572003-10-0303 October 2003 Relief Request No. 7, Fourth 10-Year Interval Inservice Inspection Program Plan L-MT-03-045, Request for Approval of Inservice Inspection Program Third 10-Year Interval Relief Request No. 172003-08-27027 August 2003 Request for Approval of Inservice Inspection Program Third 10-Year Interval Relief Request No. 17 ML0320605802003-08-0707 August 2003 Relief, Fourth 10-Year Interval Inservice Testing Program ML0317002092003-07-17017 July 2003 Relief Request, Nos. PR-01, PR-02, PR-03, PR-04, PR-05, and VR-02 Related to the Fourth 10-Year Interval Inservice Testing Program L-MT-03-048, Request for Authorization of Inservice Inspection Program Fourth 10-Year Interval Relief Request No. 82003-06-12012 June 2003 Request for Authorization of Inservice Inspection Program Fourth 10-Year Interval Relief Request No. 8 ML0316008642003-06-0909 June 2003 Relief Request, Fourth 10-Year Interval Inservice Inspection Program Plan Relief Request No. 5, TAC No. MB6956 ML0314001192003-05-19019 May 2003 Relief, Third 10-Year Interval Inservice Inspection Relief Request No 16, Parts a, B, and C L-MT-03-001, Relief Request No. Pr 06 for Fourth 10-Year Inservice Testing Interval - High Pressure Coolant Injection Pump Testing2003-05-0606 May 2003 Relief Request No. Pr 06 for Fourth 10-Year Inservice Testing Interval - High Pressure Coolant Injection Pump Testing 2024-08-27 |
Text
Retrieved from "https://kanterella.com/w/index.php?title=ML12180A588&oldid=538949"