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Category:E-Mail
MONTHYEARML24284A2822024-10-0707 October 2024 Cover Email Re Monticello SLRA-3rd Round Request for Additional Information ML24254A3932024-08-26026 August 2024 SLRA - 2nd Round Request for Additional Information ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24131A0802024-05-10010 May 2024 Final RAI for LAR to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML24036A2462024-04-24024 April 2024 NRC to Fws, NRC Issuance of Draft Environmental Impact Statement for Monticello Subsequent License Renewal, Opportunity for Public Comment, and Endangered Species Act Determinations ML24092A2152024-03-27027 March 2024 Email: Requests for Information to Support Deis ML24068A0612024-03-0707 March 2024 Extension of Audit for License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6 ML24064A1802024-03-0404 March 2024 Acceptance of Relief Request RR-017, Inservice Inspection (ISI) Impracticality During the Fifth Ten-Year Interval ML24036A0932024-02-0202 February 2024 Acceptance of License Amendment Request to Revise TS 5.6.5 and Update PTLR Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data ML24022A0212024-01-20020 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 ML22175A1602022-06-24024 June 2022 NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection ML22181A1962022-06-24024 June 2022 NRR E-mail Capture - Draft RAI Monticello Alternative VR-08 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 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 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 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 2024-08-05
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Accession No. ML101130510 From: Tam, Peter Sent: Friday, April 23, 2010 2:38 PM To: 'Loeffler, Richard A.'; Speight, Steven; Salamon, Gabor Cc: Pascarelli, Robert; Mitchell, Matthew; Purtscher, Patrick; Haeg, Lucas; Riemer, Kenneth; Thomas, Christopher
Subject:
Monticello - Record of conference call conveying verbal approval of Relief Request No. 18 (TAC ME3593)
Rick:
By letter dated April 2, 2010, Northern States Power Company - Minnesota (the licensee) requested NRC approval to implement an alternative (L-MT-10-023) to certain requirements of the 1995 Edition through the 1996 addenda of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for Monticello Nuclear Generating Station (Monticello). The alternative was requested under the provisions of Title 10 of the Code of Federal Regulations (CFR) 50.55a(a)(3)(i). The proposed alternative is to ASME Code,Section XI, IWC-3120 on Inservice Volumetric and Surface Exams. Under this request, the licensee would be applying ASME Code Case N-705, Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2 or 3 Vessels and Tanks, to evaluate the leakage observed from an ASME Code Class 2 standby liquid control (SLC) tank that operates at atmospheric pressure.
On March 19, 2010, a white, crystalline substance was discovered at the base of SLC tank T-200. The area was reinspected on March 22, 2010, and moisture was present where the white, crystalline substance was previously found. Subsequent nondestructive evaluation (NDE) revealed multiple cracks in the base plate around the circumference of the tank, one of which was longer than the others and served as a path for water to leak out of the SLC tank. The licensee has attributed this leak to transgranular stress corrosion cracking of the base plate (304 stainless steel) of the SLC tank.
The licensees alternative to the stated ASME Code requirement is to apply ASME Code Case N-705 as the evaluation criteria for temporary acceptance of the degradation in the Monticello SLC tank. This Code Case is accepted as part of the Cases of the ASME Boiler and Pressure Vessel Code, but is not yet officially accepted by the NRC. Application of this Code Case requires the licensee to follow the steps outlined below:
- 1. characterize the degradation and determine that the current condition of the tank or vessel is acceptable,
- 2. determine if the degradation can be bounded or perform a structural integrity evaluation to calculate a time for the degradation, considering all potential degradation growth mechanisms over the period of evaluation, to reach a maximum acceptable size,
- 3. monitor conditions daily to ensure leakage/structural integrity does not exceed acceptable limits, and
- 4. repair/replace the tank or vessel per ASME Code requirements before the degradation reaches the maximum acceptable size or within the prescribed time frame for the
specific situation (not to exceed 26 months from the discovery of the degradation), which ever is less.
The licensee provided information to demonstrate that the proposed alternative would maintain an acceptable level of quality and safety under all licensing basis conditions of operation until the next refueling outage starts in March 2011 (12 months from discovery of the degradation). The NRC staff has considered the submittal on leakage from the T-200 SLC tank at Monticello and concludes that the methodology provided by ASME Code Case N-705 provides an acceptable alternative, because the alternative represents an acceptable level of quality and safety in accordance with 10 CFR 50.55a(a)(3)(i).
The NRC has completed its review of the information provided in the licensees submittal for proposed alternative L-MT-10-023 regarding the use of ASME Code Case N-705. The NRC staff has concluded that the information provided by the licensee is consistent with the provisions of 10 CFR 50.55a(a)(3)(i) and supports the granting of the proposed alternative to ASME Code requirements. Accordingly, following the guidance in NRR Office Instruction LIC-102, "Review of Relief Requests," Rev. 2, the chiefs of the NRCs Vessel and Internals Integrity Branch (CVIB) and the Plant Licensing Branch III-1 (LPL3-1) verbally affirmed the authorization for the licensee to implement the proposed alternative in accordance with the information provided in the licensees letter dated April 2, 2010. The authorization is immediately effective, and will remain in effect until the next refueling outage in March 2011. The NRC staff will follow up in writing in 150 days or less.
NRC participants were:
Robert Pascarelli (LPL3-1, Office of NRR)
Matthew Mitchell (CVIB, Office of NRR)
Peter Tam (LPL3-1, Office of NRR)
Licensee participants were:
T. O'Connor (Site VP),
N. Haskell (Director Site Engineering)
S. Porter (Engineering Programs Manager)
S. Speight (Regulatory Affairs Manager)
G. Sherwood (Supervisor Inspection and Materials)
R. Deopere (Principal Engineering Analyst (ISI Coordinator))
F. Poteet (True North Engineering (ISI Consultant))
R. Loeffler (Senior Licensing Engineer)
Peter S. Tam Senior Project Manager (for Kewaunee and Monticello)
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 ()
Subject:
Monticello - Record of conference call conveying verbal approval of Relief Request No. 18 (TAC ME3593)
Sent Date: 04/23/2010 2:26:32 PM Received Date: 04/23/2010 2:37:00 PM From: Tam, Peter Created By: Peter.Tam@nrc.gov Recipients:
Richard.Loeffler@xenuclear.com ('Loeffler, Richard A.')
Tracking Status: None Steven.Speight@xenuclear.com (Speight, Steven)
Tracking Status: None Gabor.Salamon@xenuclear.com (Salamon, Gabor)
Tracking Status: None Robert.Pascarelli@nrc.gov (Pascarelli, Robert)
Tracking Status: None Matthew.Mitchell@nrc.gov (Mitchell, Matthew)
Tracking Status: None Patrick.Purtscher@nrc.gov (Purtscher, Patrick)
Tracking Status: None Lucas.Haeg@nrc.gov (Haeg, Lucas)
Tracking Status: None Kenneth.Riemer@nrc.gov (Riemer, Kenneth)
Tracking Status: None Christopher.Thomas@nrc.gov (Thomas, Christopher)
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 28907 04/23/2010 Options Expiration Date:
Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received: