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| | document type = E-Mail | | | document type = E-Mail |
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| | | project = TAC:ME8088, TAC:ME8088, TAC:ME8089, TAC:ME8090, TAC:ME8091, TAC:ME8092, TAC:ME8093, TAC:ME8094, TAC:ME8095, TAC:ME8096 |
| | | stage = Other |
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| | {{#Wiki_filter:Accession No. ML12086A005 From: Tam, Peter Sent: Friday, March 23, 2012 11:07 AM To: Loeffler, Richard A.; Rippy, L. Randal Cc: Hatchett, Gregory Subject: Acceptance Review for Relief Requests conveyed by NSPM letter of 9/28/2011 (TAC ME8088 - ME8096) Rick, Randall: |
| | The NRC staff found the following relief requests conveyed by NSPM's 9/28/2011 letter acceptable for review in accordance with NRR Office Instruction LIC-109: |
| | * Relief Request IST VR-03 for 5th interval |
| | * Relief Request IST VR-02 for 5th Interval |
| | * Relief Request IST VR-01 for 5th interval |
| | * Relief Request IST PR-06 for 5th interval |
| | * Relief Request IST PR-05 for 5th interval |
| | * Relief Request IST PR-04 for 5th interval |
| | * Relief Request IST PR-03 for 5th interval |
| | * Relief Request IST PR-02 for 5th interval |
| | * Relief Request IST PR-01 for 5th interval With respect to Relief Request IST PR-03, HPCI pump vibration, the NRC staff needs clarification of the basis for the consultants analysis which the licensees relies on, in part, to demonstrate the acceptably of the vibration in the vertical direction being in the alert range without requiring the additional testing specified in the OM Code. Further, the licensee asserts industry history demonstrates no failures have been attributed to extended hours of pump operation at vibration levels exceeding 0.325 in/Sec were found. It is unclear what industry history the licensee is referring and it would be helpful if the licensee would clarify this statement. Possibly you can communicate the clarification by a phone call or e-mail. Peter S. Tam Senior Project Manager (for D. C. Cook and Monticello) Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451 |
| }} | | }} |
Revision as of 05:00, 2 April 2018
Letter Sequence Acceptance Review |
|---|
TAC:ME8088, (Approved, Closed) TAC:ME8088, (Approved, Closed) TAC:ME8089, (Approved, Closed) TAC:ME8090, (Approved, Closed) TAC:ME8091, (Approved, Closed) TAC:ME8092, (Approved, Closed) TAC:ME8093, (Approved, Closed) TAC:ME8094, (Approved, Closed) TAC:ME8095, (Approved, Closed) TAC:ME8096, (Approved, Closed) |
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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
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Final RAI for LAR to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6
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NRC to Fws, NRC Issuance of Draft Environmental Impact Statement for Monticello Subsequent License Renewal, Opportunity for Public Comment, and Endangered Species Act Determinations
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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
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NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f)
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ML23268A0292023-09-20020 September 2023
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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)
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NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports
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NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request VR-11 for MO-2397
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SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen
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SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos
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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
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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)
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NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing
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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
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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
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NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related RHR and RHRSW Pump Testing
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ML21256A1862021-09-13013 September 2021
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ML21256A1892021-09-13013 September 2021
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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
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ML21252A0132021-08-31031 August 2021
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NRR E-mail Capture - Monticello TSTF-505, Request for Additional Information
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2024-08-05
[Table view] |
Text
Accession No. ML12086A005 From: Tam, Peter Sent: Friday, March 23, 2012 11:07 AM To: Loeffler, Richard A.; Rippy, L. Randal Cc: Hatchett, Gregory Subject: Acceptance Review for Relief Requests conveyed by NSPM letter of 9/28/2011 (TAC ME8088 - ME8096) Rick, Randall:
The NRC staff found the following relief requests conveyed by NSPM's 9/28/2011 letter acceptable for review in accordance with NRR Office Instruction LIC-109:
- Relief Request IST VR-03 for 5th interval
- Relief Request IST VR-02 for 5th Interval
- Relief Request IST VR-01 for 5th interval
- Relief Request IST PR-06 for 5th interval
- Relief Request IST PR-05 for 5th interval
- Relief Request IST PR-04 for 5th interval
- Relief Request IST PR-03 for 5th interval
- Relief Request IST PR-02 for 5th interval
- Relief Request IST PR-01 for 5th interval With respect to Relief Request IST PR-03, HPCI pump vibration, the NRC staff needs clarification of the basis for the consultants analysis which the licensees relies on, in part, to demonstrate the acceptably of the vibration in the vertical direction being in the alert range without requiring the additional testing specified in the OM Code. Further, the licensee asserts industry history demonstrates no failures have been attributed to extended hours of pump operation at vibration levels exceeding 0.325 in/Sec were found. It is unclear what industry history the licensee is referring and it would be helpful if the licensee would clarify this statement. Possibly you can communicate the clarification by a phone call or e-mail. Peter S. Tam Senior Project Manager (for D. C. Cook and Monticello) Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451
