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| {{#Wiki_filter:Accession No. ML090820031 | | {{#Wiki_filter:Accession No. ML090820031 From: Peter Tam Sent: Friday, March 20, 2009 4:21 PM To: 'Pointer, Kenneth'; 'Salamon, Gabor' Cc: Roger Pedersen; Karl Feintuch |
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| From: Peter Tam Sent: Friday, March 20, 2009 4:21 PM To: 'Pointer, Kenneth'; 'Salamon, Gabor' Cc: Roger Pedersen; Karl Feintuch | |
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| ==Subject:== | | ==Subject:== |
| Monticello - Draft RAI from re. Reactor Inspection Branch re. Proposed EPU Amendment (TAC MD9990) | | Monticello - Draft RAI from re. Reactor Inspection Branch re. Proposed EPU Amendment (TAC MD9990) |
| Ken: Our review of your 11/5/09 application for an extended power uprate (EPU) amendment is ongoing. Our Reactor Inspection Branch has provided the following draft RAI questions in the health physics area. Please contact me to set up a conference call to discuss these questions. If you desire to have the proposed conference call during 3/24/09 - 4/10/09 when I am on leave, please contact my back up Karl Feintuch (301-415-3079). | | Ken: |
| : 1. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-343, indicates that an analysis predicts only a 3 percent increase in dose rates at the high pressure (HP) turbine due to increased N-16 in the steam entering the turbine. This is somewhat lower than analysis provided for similar uprates at other BWRs in the U.S. | | Our review of your 11/5/09 application for an extended power uprate (EPU) amendment is ongoing. Our Reactor Inspection Branch has provided the following draft RAI questions in the health physics area. Please contact me to set up a conference call to discuss these questions. |
| | If you desire to have the proposed conference call during 3/24/09 - 4/10/09 when I am on leave, please contact my back up Karl Feintuch (301-415-3079). |
| | : 1. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-343, indicates that an analysis predicts only a 3 percent increase in dose rates at the high pressure (HP) turbine due to increased N-16 in the steam entering the turbine. This is somewhat lower than analysis provided for similar uprates at other BWRs in the U.S. |
| : a. Provide a detailed description of this analysis and input parameters. Include the main steam transient time, from the reactor head to the HP-LP turbine crossover line under full power CLTP conditions; and the corresponding transient time under full power EPU conditions. | | : a. Provide a detailed description of this analysis and input parameters. Include the main steam transient time, from the reactor head to the HP-LP turbine crossover line under full power CLTP conditions; and the corresponding transient time under full power EPU conditions. |
| : b. It is the staff's understanding that the steam crossover line from the HP to LP turbines is the major source of N-16 gamma radiation shine from BWR turbine buildings. Verify that this is the case for Monticello or provide the transient time information in 1.a. above from the reactor head to the turbine building component determined to be the major gamma source. | | : b. It is the staffs understanding that the steam crossover line from the HP to LP turbines is the major source of N-16 gamma radiation shine from BWR turbine buildings. Verify that this is the case for Monticello or provide the transient time information in 1.a. above from the reactor head to the turbine building component determined to be the major gamma source. |
| : 2. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-344, indicates that "EPU may result in a maximum sky shine source dose rate increase of up to 34.4 percent" and that this results in a maximum increase in offsite dose due to sky shine at EPU conditions of less than 6 mrem/yr. | | : 2. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-344, indicates that EPU may result in a maximum sky shine source dose rate increase of up to 34.4 percent and that this results in a maximum increase in offsite dose due to sky shine at EPU conditions of less than 6 mrem/yr. |
| : a. Resolve the apparent discrepancy between the 3 percent increase stated on page 2-343 and the 34.4 percent increase stated on page 2-344. | | : a. Resolve the apparent discrepancy between the 3 percent increase stated on page 2-343 and the 34.4 percent increase stated on page 2-344. |
| : b. Describe how Monticello currently demonstrates that the annual dose to the maximum exposed member of the public meets the 25 mrem/yr requirement of | | : b. Describe how Monticello currently demonstrates that the annual dose to the maximum exposed member of the public meets the 25 mrem/yr requirement of 40 CFR 190. |
| | | : c. What is the nominal annual dose (allowing for variations from year to year) to the maximum exposed member of the public from Monticello operations under CLTP conditions? What are the contributions to this dose from N-16 shine, Nobel Gas, and other plant effluents? |
| 40 CFR 190. c. What is the nominal annual dose (allowing for variations from year to year) to the maximum exposed member of the public from Monticello operations under CLTP conditions? What are the contributions to this dose from N-16 shine, Nobel Gas, and other plant effluents? | | : 3. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-343, Table 2.10-2, indicates a possible increase in localized dose rates in the balance-of plant (BOP) of up to 1130% under EPU conditions. |
| : 3. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-343, Table 2.10-2, indicates a possible increase in localized dose rates in the balance-of plant (BOP) of up to 1130% under EPU conditions. Verify that these increases do not change the radiation zoning of the BOP spaces. | | Verify that these increases do not change the radiation zoning of the BOP spaces. |
| : 4. The Safety Analysis Report for the Monticello Constant Power Uprate , dated October 2008, page 2-340, Table 2.9-1, indicates the dose consequences in the Control Room and Technical Support Center, from a design-basis loss-of-coolant accident under EPU conditions, as 3.80 rem and 0.83 rem, respectively. Verify that these results include direct radiation exposure from plant systems containing the accident source term, consistent with the assumptions in NUREG-0737, item II.B.2. If not, demonstrate that the direct radiation dose rates for these two vital areas meet the GDC-19 dose criteria, as specified in NUREG-0737, item II.B.2. | | : 4. The Safety Analysis Report for the Monticello Constant Power Uprate , dated October 2008, page 2-340, Table 2.9-1, indicates the dose consequences in the Control Room and Technical Support Center, from a design-basis loss-of-coolant accident under EPU conditions, as 3.80 rem and 0.83 rem, respectively. Verify that these results include direct radiation exposure from plant systems containing the accident source term, consistent with the assumptions in NUREG-0737, item II.B.2. |
| This e-mail aims solely to prepare you and others for the requested conference call. This e-mail does not convey a formal NRC staff position, and does not formally request for additional information. Peter S. Tam , Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451 | | If not, demonstrate that the direct radiation dose rates for these two vital areas meet the GDC-19 dose criteria, as specified in NUREG-0737, item II.B.2. |
| | | This e-mail aims solely to prepare you and others for the requested conference call. This e-mail does not convey a formal NRC staff position, and does not formally request for additional information. |
| E-mail Properties Mail Envelope Properties (3D6B1F4F51D25E4E9B6C93FF92DAE5171443BF3C27) | | Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451 E-mail Properties Mail Envelope Properties (3D6B1F4F51D25E4E9B6C93FF92DAE5171443BF3C27) |
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| ==Subject:== | | ==Subject:== |
| Monticello - Draft RAI from re. Reactor Inspection Branch re. Proposed EPU Amendment (TAC MD9990) | | Monticello - Draft RAI from re. Reactor Inspection Branch re. Proposed EPU Amendment (TAC MD9990) |
| Sent Date: 3/20/2009 4:21:23 PM Received Date: 3/20/2009 4:21:00 PM From: Peter Tam | | Sent Date: 3/20/2009 4:21:23 PM Received Date: 3/20/2009 4:21:00 PM From: Peter Tam Created By: Peter.Tam@nrc.gov Recipients: |
| | | Kenneth.Pointer@xenuclear.com ('Pointer, Kenneth') |
| Created By: Peter.Tam@nrc.gov | | Tracking Status: None Gabor.Salamon@xenuclear.com ('Salamon, Gabor') |
| | | Tracking Status: None Roger.Pedersen@nrc.gov (Roger Pedersen) |
| Recipients: | |
| Kenneth.Pointer@xenuclear.com ('Pointer, Kenneth') Tracking Status: None Gabor.Salamon@xenuclear.com ('Salamon, Gabor') Tracking Status: None Roger.Pedersen@nrc.gov (Roger Pedersen) | |
| Tracking Status: None Karl.Feintuch@nrc.gov (Karl Feintuch) | | Tracking Status: None Karl.Feintuch@nrc.gov (Karl Feintuch) |
| Tracking Status: None Post Office: | | Tracking Status: None |
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| MESSAGE 17372 3/20/2009
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| Priority: olImportanceNormal ReplyRequested: False Return Notification: False
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| Sensitivity: olNormal Recipients received:}} | | Post Office: |
| | HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 17372 3/20/2009 Options Expiration Date: |
| | Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received:}} |
Letter Sequence Draft RAI |
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TAC:MD9990, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis., L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008, L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008, L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538, L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac), L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009, L-MT-09-049, Drawing C.5-2007, Revision 15, Failure to Scram, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009, L-MT-09-083, Extended Power Uprate: Limit Curves Requested by the Mechanical and Civil Review Branch (Emcb) Associated with Requests for Additional Information (Rais) Dated March 20, 2009, L-MT-09-088, Extended Power Uprate: Revision to Clarify Text in Enclosures 5 and 7 of L-MT-08-052, L-MT-09-097, Extended Power Uprate: Acknowledgement of NRC Review Delay, L-MT-10-025, Extended Power Uprate (Epu): Response to NRC-NSPM February 25, 2010 Conference Call, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information, L-MT-11-044, Uprate (Epu): Update on EPU Commitments, L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer., L-MT-12-114, Drawing C.5-2007, Rev. 17, Failure to Scram, L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis, L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project., L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14, L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan, L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages, L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit, L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications, L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report., L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology, L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML083230111, ML083400402, ML083500575, ML083570610, ML083590127, ML090710680, ML090710683, ML090710684, ML091120578, ML091140470, ML091410121, ML091410122, ML091410123, ML091410124, ML091760769, ML092290250, ML092810554, ML093160816, ML093220925, ML093220964, ML093620024, ML100280558... further results
|
MONTHYEARML0907106832008-02-17017 February 2008
Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Attachment 1-1g Through End of Encl. 1
Project stage: Other
ML13064A4352008-03-20020 March 2008
CA-95-075, Main Steam Line High Flow Setpoint, Attachment 4
Project stage: Other
ML0914101242008-08-11011 August 2008
Monticello - Calculation CA-08-050, Rev. 0, Instrument Setpoint Calculation - Average Power Range Monitor (APRM) Non-Flow Eiased Prnm Setpoints for Cl Tp and EPU
Project stage: Other
L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.2008-10-31031 October 2008
Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.
Project stage: Other
ML0832301122008-10-31031 October 2008
NEDC-33322-NP, Revision 3, Monticello Nuclear Generating Plant, Safety Analysis Report, Constant Pressure Power Uprate.
Project stage: Request
ML0832301112008-11-0505 November 2008
Monticello Nuclear Generating Plant, License Amendment Request: Extended Power Uprate
Project stage: Other
ML0832301142008-11-0505 November 2008
Monticello Nuclear Generating Plant, Steam Dryer Dynamic Stress Evaluation.
Project stage: Request
ML0834003662008-12-0202 December 2008
Extended Power Uprate Acceptance Review Questions on Probabilistic Risk Assessment Issues
Project stage: Acceptance Review
ML0834004022008-12-0505 December 2008
Extended Power Uprate - Monticello - Request to Supplement the Application in the Probabilistic Risk Assessment Area
Project stage: Other
ML0835000992008-12-11011 December 2008
Monticello Extended Power Uprate (Usnrc TAC MD9990): Acceptance Review Supplement Regarding Steam Dryer Outer Hood Submodel Analysis
Project stage: Supplement
ML0835303022008-12-16016 December 2008
Draft Request for Additional Information, Environmental Issues of EPU Application
Project stage: Draft RAI
ML0936200242008-12-18018 December 2008
Report 0800760.401, Rev. 1, Flaw Evaluation and Vibration Assessment of Existing Monticello Steam Dryer Flaws for Extended Power Uprate.
Project stage: Other
ML0835005752008-12-18018 December 2008
Letter Finding 11/5/08 Application for Amendment Acceptable for Review
Project stage: Other
ML0835309982008-12-18018 December 2008
EPU Application - Additional RAI Question Regarding an Environmental Issue
Project stage: RAI
ML0835310022008-12-18018 December 2008
Proposed Eou Amendment - Revised RAI Re. Containment Analysis
Project stage: RAI
ML0914101222008-12-18018 December 2008
Monticello - Calculation CA-95-075, Revision 1, Main Steam Line High Flow Setpoint
Project stage: Other
ML0914101212008-12-19019 December 2008
Monticello - Calculation CA-95-073, Revision 4, Reactor Low Water Level SCRAM Setpoint
Project stage: Other
ML0835901272009-01-14014 January 2009
Letter Conveying Determination That Enclosure 5 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Withheld from Public Disclosure
Project stage: Other
ML0835706102009-01-26026 January 2009
Letter Conveying Determination That Enclosure 11 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Is Withheld from Public Disclosure
Project stage: Other
L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 20082009-01-29029 January 2009
Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008
Project stage: Other
L-MT-09-005, Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate2009-02-0404 February 2009
Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate
Project stage: Request
L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 20082009-02-0404 February 2009
Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008
Project stage: Other
ML0904204852009-02-11011 February 2009
Draft RAI from Materials Engineering Re. Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0907106792009-02-17017 February 2009
Monticello, Response to NRC Containment & Ventilation Branch Request for Additional Information (Rals) Dated December 18, 2008
Project stage: Request
ML0907106802009-02-17017 February 2009
Monticello, Enclosure 1 to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 1 Dated December 18, 2008, Cover Through Copy of MNGP Appr T0406 Data Transmittal Page 424 of 424
Project stage: Other
L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 5382009-02-17017 February 2009
Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538
Project stage: Other
ML0907106842009-02-17017 February 2009
Enclosures 2 - 4: NSPM Response to Containment & Ventilation Branch RAI Numbers 2, 3 and 4 Dated December 18, 2008
Project stage: Other
L-MT-09-018, Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 20092009-02-24024 February 2009
Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 2009
Project stage: Request
ML0907100912009-03-11011 March 2009
Conveying Draft RAI Questions from the Instrumentation and Controls Branch Regarding the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0907200572009-03-12012 March 2009
Conveys Draft RAI Regarding Fire Protection for the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0907800062009-03-18018 March 2009
Draft RAI from Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0907800042009-03-18018 March 2009
Conveys Draft RAI by the PRA Licensing Branch on the Proposed EPU Amendment
Project stage: Draft RAI
ML0907809032009-03-19019 March 2009
Conveys Draft RAI Provided by the Containment and Ventilation Branch on the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0907809092009-03-19019 March 2009
RAI from the Containment and Ventilation Branch the Proposed Extended Power Uprate Amendment
Project stage: RAI
L-MT-09-017, Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 20092009-03-19019 March 2009
Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 2009
Project stage: Request
ML0908200312009-03-20020 March 2009
Draft RAI Re. Health Physics Issues for the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0908200992009-03-23023 March 2009
Draft RAI from the Balance of Plant Branch Re the Proposed Amendment on Extended Power Uprate
Project stage: Draft RAI
ML0908800022009-03-28028 March 2009
Second Portion of Draft RAI from the Mechanical and Civil Engineering Branch Regarding the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0908800032009-03-28028 March 2009
Draft RAI from the Electrical Engineering Branch Re. the Proposed Extended Power Uprate Amendment for Monticello
Project stage: Draft RAI
ML0908800012009-03-29029 March 2009
Additional Draft RAI Questions from the Containment and Ventilation Branch Proposed EPU Amendment for Monticello
Project stage: Draft RAI
ML0910300212009-04-0606 April 2009
Draft RAI Question from Instrumentation and Controls Branch Re. Proposed EPU Amendment
Project stage: Draft RAI
ML0910300172009-04-0606 April 2009
Conveys an Additional EPU Draft RAI Question from Instrumentation and Controls Branch
Project stage: Draft RAI
L-MT-09-025, Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 20092009-04-22022 April 2009
Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 2009
Project stage: Request
ML0911205782009-04-22022 April 2009
Request for Audit of Implementation of Long-Term Stability Solution
Project stage: Other
ML0911902092009-04-29029 April 2009
Transmit Revised Draft RAI from the Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0914101232009-05-0606 May 2009
Monticello - Calculation 96-054, Rev 5, Turbine Stop Valve Closure/Generator Load Reject Scram Bypass
Project stage: Other
ML0911404702009-05-0707 May 2009
Determination That Submitted Information Can Be Withheld from Public Disclosure
Project stage: Other
ML0914101202009-05-13013 May 2009
Monticello - Extended Power Uprate: Response to NRC Instrumentation & Controls Branch Request for Additional Information Dated March 11, 2009, and April 6, 2009, and Fire Protection Branch RAIs Dated March 12, 2009
Project stage: Request
L-MT-09-045, Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 20092009-05-26026 May 2009
Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 2009
Project stage: Request
L-MT-09-029, Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 20092009-05-29029 May 2009
Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 2009
Project stage: Request
2009-02-24
[Table View] |
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Category:E-Mail
MONTHYEARML24022A0212024-01-20020 January 2024
NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f)
ML23353A0742023-12-19019 December 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Proposed Alternative VR-09, Modifications to OMN-17
ML23348A3462023-12-14014 December 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6
ML23268A0292023-09-20020 September 2023
SLRA - Requests for Confirmation of Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen
ML23249A2092023-09-0606 September 2023
NRR E-mail Capture - Action: Opportunity to Review and Comment on a New NRC Information Collection, 10 CFR Part 50.55a, Codes and Standards (3150-XXXX)
ML23248A3462023-09-0505 September 2023
NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports
ML23237A4822023-08-25025 August 2023
SLRA - Request for Additional Information - Set 3 - Email from Marieliz Johnson to Shawn Hafen
ML23228A1212023-08-16016 August 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request VR-11 for MO-2397
ML23227A2182023-08-15015 August 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request RR-002 to Use IWB-2500(f)
ML23219A1072023-08-0707 August 2023
SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen
ML23200A3502023-07-19019 July 2023
SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos
ML23172A1122023-06-21021 June 2023
SLRA - Requests for Confirmation of Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos
ML23054A3322023-02-23023 February 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for ISI Program Code of Record
ML23053A1362023-02-13013 February 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for Cisi Program
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)
ML23004A1982023-01-0404 January 2023
NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing
ML23012A2102022-07-26026 July 2022
Letter Submitting Monticello Outline Package
ML22181A1962022-06-24024 June 2022
NRR E-mail Capture - Draft RAI Monticello Alternative VR-08
ML22175A1602022-06-24024 June 2022
NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection
ML22131A2652022-05-11011 May 2022
NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island
ML22123A2822022-05-0303 May 2022
NRR E-mail Capture - Request for Additional Information Monticello Alternative VR-10, EFCV Testing Frequency
ML22101A0712022-04-11011 April 2022
NRR E-mail Capture - Monticello - Acceptance of Requested Licensing Action License Amendment Request to Revise TS 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency
ML22089A1302022-03-30030 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Related Excess Flow Check Valve Testing Frequency
ML22082A1812022-03-23023 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-08 Alternative to Adopt ASME OM Code Case OMN-28
ML22075A2612022-03-16016 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-07 Alternative Related to MOV Testing Per ASME OM Code Case OMN-26
ML22067A2032022-03-0808 March 2022
Audit Plan to Support Review of an Amendment to Transition to Atrium 11 Fuel (Redacted)
ML22011A0642022-01-11011 January 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Support Diesel Generator Fuel Oil Storage Tank Inspection
ML22005A3612022-01-0505 January 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pump Vibration Testing Per ASME OM Code Case OMN-22
ML21347A0082021-12-10010 December 2021
NRR E-mail Capture - Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested License Amendment Standard Emergency Plan and Consolidated Emergency Operations Facility
ML21330A0382021-11-18018 November 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related RHR and RHRSW Pump Testing
ML21286A7882021-10-0606 October 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Residual Heat Removal Heat Exchanger Flow Control Valve Stroke Timing
ML21256A1892021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Testing the Control Rod Drive Scram Discharge Header Check Valves
ML21256A1862021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to HPCI and RCIC Pump Testing
ML21256A1882021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Vibration Testing Range for the Sblc Pumps
ML21253A2002021-09-10010 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pressure Isolation Valve Testing
ML21252A0132021-08-31031 August 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt Advanced Framatome Methodologies
ML21130A3022021-05-0707 May 2021
Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System
ML21110A7042021-04-20020 April 2021
Response: Monticello Nuclear Plant Outage - Covid Risk to On-Site Employees
ML21084A2522021-03-24024 March 2021
NRR E-mail Capture - Revised Review Schedule for Monticello TSTF-505 (EPID L-20200LLA-0062)
ML21068A2772021-03-0909 March 2021
NRR E-mail Capture - Monticello TSTF-505, Request for Additional Information
ML20343A1292020-12-0808 December 2020
NRR E-mail Capture - Request for Additional Information
ML20342A1782020-12-0707 December 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-564 Safety Limit MCPR
ML20302A1972020-10-26026 October 2020
NRR E-mail Capture - Monticello Request for Additional Information TSTF-505 License Amendment Request
ML20289A1072020-10-0606 October 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582 Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements (EPID L-2020-LLA-0209
ML20191A0252020-07-0101 July 2020
NRR E-mail Capture - Draft Request for Additional Information Monticello Alternative Request RR-016 Related to H8, H9, and H 10 Weld Examinations
ML20120A0272020-04-28028 April 2020
NRR E-mail Capture - Request for Additional Information Monticello Long Term Steam Dryer Inspection Plan
ML20099F1292020-04-0606 April 2020
E-mail to Licensee for Monticello Lr Phase 4 RFI
ML20077L4632020-03-17017 March 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 -Acceptance of Requested Licensing Action Request to Adopt TSTF-529
ML20064C5352020-03-0404 March 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Revise the Previously Authorized Alternative in RR-008 for the H8 and H9 Welds
2024-01-20
[Table view] |
Text
Accession No. ML090820031 From: Peter Tam Sent: Friday, March 20, 2009 4:21 PM To: 'Pointer, Kenneth'; 'Salamon, Gabor' Cc: Roger Pedersen; Karl Feintuch
Subject:
Monticello - Draft RAI from re. Reactor Inspection Branch re. Proposed EPU Amendment (TAC MD9990)
Ken:
Our review of your 11/5/09 application for an extended power uprate (EPU) amendment is ongoing. Our Reactor Inspection Branch has provided the following draft RAI questions in the health physics area. Please contact me to set up a conference call to discuss these questions.
If you desire to have the proposed conference call during 3/24/09 - 4/10/09 when I am on leave, please contact my back up Karl Feintuch (301-415-3079).
- 1. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-343, indicates that an analysis predicts only a 3 percent increase in dose rates at the high pressure (HP) turbine due to increased N-16 in the steam entering the turbine. This is somewhat lower than analysis provided for similar uprates at other BWRs in the U.S.
- a. Provide a detailed description of this analysis and input parameters. Include the main steam transient time, from the reactor head to the HP-LP turbine crossover line under full power CLTP conditions; and the corresponding transient time under full power EPU conditions.
- b. It is the staffs understanding that the steam crossover line from the HP to LP turbines is the major source of N-16 gamma radiation shine from BWR turbine buildings. Verify that this is the case for Monticello or provide the transient time information in 1.a. above from the reactor head to the turbine building component determined to be the major gamma source.
- 2. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-344, indicates that EPU may result in a maximum sky shine source dose rate increase of up to 34.4 percent and that this results in a maximum increase in offsite dose due to sky shine at EPU conditions of less than 6 mrem/yr.
- a. Resolve the apparent discrepancy between the 3 percent increase stated on page 2-343 and the 34.4 percent increase stated on page 2-344.
- b. Describe how Monticello currently demonstrates that the annual dose to the maximum exposed member of the public meets the 25 mrem/yr requirement of 40 CFR 190.
- c. What is the nominal annual dose (allowing for variations from year to year) to the maximum exposed member of the public from Monticello operations under CLTP conditions? What are the contributions to this dose from N-16 shine, Nobel Gas, and other plant effluents?
- 3. The Safety Analysis Report for the Monticello Constant Power Uprate, dated October 2008, page 2-343, Table 2.10-2, indicates a possible increase in localized dose rates in the balance-of plant (BOP) of up to 1130% under EPU conditions.
Verify that these increases do not change the radiation zoning of the BOP spaces.
- 4. The Safety Analysis Report for the Monticello Constant Power Uprate , dated October 2008, page 2-340, Table 2.9-1, indicates the dose consequences in the Control Room and Technical Support Center, from a design-basis loss-of-coolant accident under EPU conditions, as 3.80 rem and 0.83 rem, respectively. Verify that these results include direct radiation exposure from plant systems containing the accident source term, consistent with the assumptions in NUREG-0737, item II.B.2.
If not, demonstrate that the direct radiation dose rates for these two vital areas meet the GDC-19 dose criteria, as specified in NUREG-0737, item II.B.2.
This e-mail aims solely to prepare you and others for the requested conference call. This e-mail does not convey a formal NRC staff position, and does not formally request for additional information.
Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451 E-mail Properties Mail Envelope Properties (3D6B1F4F51D25E4E9B6C93FF92DAE5171443BF3C27)
Subject:
Monticello - Draft RAI from re. Reactor Inspection Branch re. Proposed EPU Amendment (TAC MD9990)
Sent Date: 3/20/2009 4:21:23 PM Received Date: 3/20/2009 4:21:00 PM From: Peter Tam Created By: Peter.Tam@nrc.gov Recipients:
Kenneth.Pointer@xenuclear.com ('Pointer, Kenneth')
Tracking Status: None Gabor.Salamon@xenuclear.com ('Salamon, Gabor')
Tracking Status: None Roger.Pedersen@nrc.gov (Roger Pedersen)
Tracking Status: None Karl.Feintuch@nrc.gov (Karl Feintuch)
Tracking Status: None
Post Office:
HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 17372 3/20/2009 Options Expiration Date:
Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received:
