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TAC:MC8971, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) |
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MONTHYEARML0534003682005-12-12012 December 2005 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0604502112006-02-17017 February 2006 Notice of Meeting with Nuclear Management Company, LLC, Monticello Nuclear Generating Plant, Regarding Full-Scope Application of Alternative Source Term Methodology Project stage: Meeting ML0613104452006-04-13013 April 2006 Monticello - Full Scope Alternate Source Term - Supplemental Information, Description of Meteorological Data Project stage: Request ML0611103102006-05-11011 May 2006 Withholding from Public Disclosure, Compact Disk 2 of 2, Alternative Source Term Supplemental Information, Submitted by Letter Dated 04/13/2006 in Support of Application for Amendments to Use Alternative Source Term Methodology Project stage: Other ML0618604632006-06-29029 June 2006 Draft RAI (Radiological) Re. Full-Scope Application of Alternative Source Term Project stage: Draft RAI ML0623500462006-08-21021 August 2006 Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST) Project stage: Supplement L-MT-06-054, Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST)2006-08-21021 August 2006 Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST) Project stage: Supplement L-MT-06-059, Response to Request for Additional Information to License Amendment Request for Full Scope Alternative Source Term2006-08-22022 August 2006 Response to Request for Additional Information to License Amendment Request for Full Scope Alternative Source Term Project stage: Response to RAI ML0628606312006-10-0606 October 2006 Draft SE for Alternative Source Term Amendment, Monticello Nuclear Generating Plant Project stage: Draft Approval ML0627900152006-12-0707 December 2006 License Amendment 148 Regarding Full-Scope Implementation of the Alternative Source Term Methodology Project stage: Approval ML0624105072006-12-0707 December 2006 Exemption from Certain Requirements of 10 CFR 50, Appendix J Project stage: Approval ML0634205172006-12-0707 December 2006 Tech Spec Pages for Amendment 148 Regarding Full-Scope Implementation of the Alternative Source Term Methodology Project stage: Acceptance Review ML0709900892007-04-17017 April 2007 Correction of Errors in Safety Evaluation Associated with Amendment No. 148 Regarding Alternative Source Term Project stage: Approval ML0906100352009-03-0909 March 2009 Correction of Inadvertent Errors on Two TS Pages in Amendment No. 148 Project stage: Other 2006-05-11
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Category:Letter
MONTHYEARML24283A1192024-10-28028 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 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 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 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 ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24164A2402024-06-10010 June 2024 Minnesota State Historic Preservation Office- Comments on Draft Monticello SLR Draft EIS L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 ML24137A2792024-06-0303 June 2024 Audit Summary for License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report ML24135A1902024-05-14014 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report IR 05000263/20240102024-05-13013 May 2024 Age-Related Degrading Inspection Report 05000263/2024010 ML24128A0042024-05-0909 May 2024 Letter to Minnesota State Historic Preservation Office- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renewal Application ML24127A1472024-05-0909 May 2024 Letter to Mille Lacs Band- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renew. Application L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000263/20240012024-04-29029 April 2024 Plan - Integrated Inspection Report 05000263/2024001 ML24115A2902024-04-25025 April 2024 Sec106 Tribal, Jackson-Street, Lonna-Spirit Lake Nation ML24115A2872024-04-25025 April 2024 Sec106 Tribal, Dupuis, Kevin-Fond Du Lac Band of Lake Superior Chippewa ML24115A2932024-04-25025 April 2024 Sec106 Tribal, Johnson, Grant-Prairie Island Indian Community ML24115A3062024-04-25025 April 2024 Sec106 Tribal, Wassana, Reggie-Cheyenne and Arapaho Tribes 05000263/LER-2024-001, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component2024-04-25025 April 2024 Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component ML24115A3032024-04-25025 April 2024 Sec106 Tribal, Taylor, Louis-Lac Courte Oreilles Band of Lake Superior Chippewa Indians ML24115A3002024-04-25025 April 2024 Sec106 Tribal, Rhodd, Timothy-Iowa Tribe of Kansas and Nebraska ML24115A2972024-04-25025 April 2024 Sec106 Tribal, Miller, Cole-Shakopee Mdewakanton Sioux Community ML24115A2962024-04-25025 April 2024 Sec106 Tribal, Larsen, Robert-Lower Sioux Indian Community ML24115A2952024-04-25025 April 2024 Sec106 Tribal, Kakkak, Gena-Menominee Indian Tribe of Wisconsin ML24115A2982024-04-25025 April 2024 Sec106 Tribal, Reider, Anthony-Flandreau Santee Sioux Tribe ML24115A2912024-04-25025 April 2024 Sec106 Tribal, Jacskon, Sr., Faron-Leech Lake Band of Ojibwe ML24115A3052024-04-25025 April 2024 Sec106 Tribal, Vanzile, Jr., Robert-Sokaogon Chippewa Community ML24115A2992024-04-25025 April 2024 Sec106 Tribal, Renville, J. Garret-Sisseton Wahpeton Oyate of the Lake Travers Reservation ML24115A3022024-04-25025 April 2024 Sec106 Tribal, Stiffarm, Jeffrey-Fort Belknap Indian Community ML24115A3072024-04-25025 April 2024 Sec106 Tribal, Williams, Jr., James-Lac Vieux Desert Band of Lake Superior Chippewa Indians ML24115A2892024-04-25025 April 2024 Sec106 Tribal, Fowler, Thomas-St. Croix Chippewa of Wisconsin 2024-09-26
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 9, 2009 Mr. Timothy J. O'Connor Site Vice President Monticello Nuclear Generating Plant Northern States Power - Minnesota 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GE!\IERATING PLANT (MNGP) - CORRECTION OF AN ERROR IN AMENDMENT NO. 148 REGARDING ALTERNATIVE SOURCE TERM METHODOLOGY (TAC NO. MC8971)
Dear Mr. O'Connor:
On December 7,2006, the Nuclear Regulatory Commission (NRC) staff issued Amendment No. 148 to Renewed Facility Operating License No. DPR-22 for MNGP, in response to your application dated September 15, 2005, as supplemented on April 13, August 21, and August 22, 2006.
Recently, Mr. R. Loeffler of your staff pointed out an error in two of the Technical Specification (TS) pages issued by Amendment No. 148. Specifically, TS pages 3.3.7.2-1 and 3.3.7.2-2 did not exist before Amendment No. 148, but the footer of these pages erroneously indicates that these pages were previously revised by Amendment No. 146, implying that these pages existed before Amendment No. 148. The erroneous footers were inadvertently introduced when the
!\IRC staff was processing Amendment No. 148. Thus, according to the NRC's policy established by SECY-96-238 (Agencywide Document Access and Management System Accession No. 9611250030), this error can be corrected by a letter. Enclosed please find the replacement Pages 3.3.7.2-1 and 3.3.7.2-2.
This correction does not change any of the conclusions in the safety evaluation associated with the amendment. We apologize if this error had caused you any inconvenience.
Sincerely*. ~~
a~m. Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosures:
As stated cc w/encls: Distribution via List Serv
Mechanical Vacuum Pump Isolation Instrumentation 3.3.7.2 3.3 INSTRUMENTATION 3.3.7.2 Mechanical Vacuum Pump Isolation Instrumentation LCO 3.3.7.2 Four channels of the Main Steam Line Tunnel Radiation - High Function for the mechanical vacuum pump isolation shall be OPERABLE.
APPLICABILITY: MODES 1 and 2 with the mechanical vacuum pump in service and any main steam line not isolated.
ACTIONS
NOTE----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable. OPERABLE status.
OR A.2 ---------------NOT E--------------
Not applicable if inoperable channel is the result of an inoperable mechanical vacuum pump breaker or isolation valve.
Place channel in trip. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B. Mechanical vacuum B.1 Restore mechanical vacuum 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> pump isolation capability pump isolation capability.
not maintained.
Corrected by letter dated March. 9, 2009 Monticello 3.3.7.2-1 Amendment No. 148
Mechanical Vacuum Pump Isolation Instrumentation 3.3.7.2 ACTIONS (continued)
CONDITION REQUIRED ACTION I COMPLETION TIME C. Required Action and C.1 Isolate the mechanical 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion vacuum pump.
Time not met.
C.2 Isolate main steam lines. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C.3 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS
N OTE----------------------------------------------------------
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains mechanical vacuum pump isolation capability.
SURVEILLANCE FREQUENCY SR 3.3.7.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.7.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.7.2.3 Perform CHANNEL CALIBRATION. The Allowable 24 months Value shall be :s 6.9 R/hour.
SR 3.3.7.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST, 24 months including mechanical vacuum pump breaker and isolation valves actuation.
Corrected by letter dated March 9, 2009 Monticello 3.3.7.2-2 Amendment No. 148
March 9, 2009 Mr. Timothy J. O'Connor Site Vice President Monticello Nuclear Generating Plant Northern States Power Minnesota B
2807 West County Road 75 Monticello, MN 55362~9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT (MNGP) - CORRECTION OF AN ERROR IN AMENDMENT NO. 146 REGARDING ALTERNATIVE SOURCr; TERM METHODOLOGY (TAC NO. MC8971)
Dear Mr. O'Connor:
On December 1, :WOf3, the Nuclear Regulatory Commission (NRC) staff issued Amendment No. 148 to RSFlewed Facility Operating License No. DPR-22 for MNGF', in response to your application dated September 15, 2005, as supplemented on April 13, August 21, and August 22, 2006.
Recently, Mr. R. Loeffler of your staff pointed out an error in two of the Technical Specification (TS) pages issued by Amendment No. 148. Specifically, T8 pages 3.3.7.2-1 afld 3.3.1.2-2 did not exist before Amendment No. 148, but the footer of these pages erroneously indicates that these pages were previously revised by Amendment No. 146, implying that these pages existed before Amendment No. 148. The erroneous footers were inadvertently introduced when the NRC staff was processing Amendment No. 148. Thus, according to the NRC's policy established by SECY-96~238 (Agencywide Document Access and Management System Accession No, 9611250030), this error can be corrected by a letter. Enclosed please find the replacement Pages 3.3.7.2-1 and 3.3.7.2~2.
This correction does not change any of the conclusions in the safety evaluation associated with tne amenelmsflt. We apologize if this error hid caused you any lncenvenlence.
Sincerely, IRAJ Peter S. Tam, Senior Project Manager Plant Licensing Braneh 111~1 Division of Operating Reactor Licensing Office of Nuclear Reactor Reguiation Docket No. 50-263
Enclosures:
As stated cc w/enols: Distribution via ListServ Di§triQU\iQO:
PUBLIC LPL3~1 rlf RidsNrrPMMonticello Resource RidsRgn3MailCenter RidsNrrLABTully RidsOgcRp RidsNrr[)orILpl:H RidsNrrDorlDpr S. Campbell, EDO Region III RiclsNrrOd RidsNrrAdes RldsAcrsAonw_MallCTR ADAMS ACCESSION NUMBER: ML090610035 OFFICE NRRlLPL3*1/PM NRRlLPL3,1/LA NRRlLPL3-1/BC NAME PTam BTuily LJames DATE 3/06/09 3/03/09 3/09/09 OFFICIAL RECORD COpy