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Category:E-Mail
MONTHYEARML24185A0912024-07-0101 July 2024 Acceptance of LAR to Revise TS Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumptions in the Accident Analyses ML24116A2532024-04-25025 April 2024 Final Request for Additional Information for LAR to Revise SR 3.8.1.2 Note 3 (EPID: L- 2023-LLA-0135) ML24045A1502024-02-15015 February 2024 Verbal Authorization for Alternative Relief Request-09 ML24045A0862024-02-12012 February 2024 Final RAI for Alternative RR-09 ML23348A3472023-12-12012 December 2023 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Minnesota Regarding a Prairie Island Nuclear Generating Plant, Units 1 & 2, Amendment ML23335A1152023-12-0101 December 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Request for Additional Information LAR to Revise TS 3.7.8 Required Actions ML23312A0882023-11-0808 November 2023 Acceptance of Request to Revise Alternatives 1-RR-5-10 and 2-RR-5-10 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 ML23207A1962023-07-26026 July 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Requested Licensing Action Request to Revise Technical Specification 3.7.8 Required Actions ML23075A2802023-03-16016 March 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Relief Requests 1-RR-5-15 and 2-RR-5-15 to Use Subsequent ASME Code Edition and Addenda ML23065A0592023-02-27027 February 2023 NRR E-mail Capture - (External_Sender) Prairie Island Request for Pre-application Meeting for Proposed LAR to Change TS 3.7.8, Condition B Required Actions ML23018A2952023-01-18018 January 2023 Acceptance of Requested Licensing Action to Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (EPID L-2022-LLA-0184) (Email) ML22167A0452022-06-16016 June 2022 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Request to Adopt TSTF-277 ML22166A4112022-06-15015 June 2022 NRR E-mail Capture - Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-08, PIV Leakage ML22160A6022022-06-0909 June 2022 NRR E-mail Capture - Draft Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, 24-Month Operating Cycle Amendment 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 ML22045A4972022-02-14014 February 2022 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Unit 2 - Acceptance of Alternative Request Alternative Related PIV Leakage Monitoring 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 ML21321A0452021-11-10010 November 2021 Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request ML21302A1252021-10-29029 October 2021 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action RTS Power Range Amendment ML21305A0102021-10-29029 October 2021 NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment ML21252A0152021-09-0202 September 2021 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Change in the Maximum Surveillance Intervals from 24 Months to 30 Months ML21252A0122021-08-30030 August 2021 NRR E-mail Capture - Request for Additional Information Amendment Request to Adopt TSTF-471 and 517-T for Prairie Island ML21133A2502021-05-13013 May 2021 NRR E-mail Capture - Prairie Island - Acceptance Review of TSTF-471 and TSTF-571-T ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20253A2782020-09-0909 September 2020 E-Mail Submitting Proposed New License Condition ML20254A1162020-09-0909 September 2020 Draft License Transmittal E-Mail ML20223A0632020-08-10010 August 2020 Email Shpo Comment Letter: Proposed License Amendment for the Prairie Island Independent Spent Fuel Storage Installation ML20192A1442020-07-0707 July 2020 NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505 ML20163A4282020-06-10010 June 2020 Email from MPCA Comment Letter - Prairie Island ISFSI ML20154K7632020-06-0202 June 2020 NRR E-mail Capture - Revision 2 to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20135G8212020-05-14014 May 2020 NRR E-mail Capture - Revision to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20112F4582020-04-21021 April 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Low Temperature Overpressure Protection ML20083F4202020-03-20020 March 2020 NRR E-mail Capture - Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) 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 ML20052C7582020-02-21021 February 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Westinghouse NSAL-09-05 and NSAL-09-05 ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML20022A1762020-01-22022 January 2020 NRR E-mail Capture - Prairie Units 1 and 2 - Acceptance of Requested Licensing Action Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements ML20021A1832020-01-21021 January 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2 ML19316A0172019-11-0101 November 2019 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Integrated Leak Rate Test Extension Request ML19253B9642019-09-10010 September 2019 NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Relief Request Adoption of Code Case N-786-3 ML19233A0032019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10 ML19193A0142019-07-0909 July 2019 NRR E-mail Capture - Acceptance of Prairie Island Nuclear Generating Plant, Units 1 and 2 Relief Request Nos. 1-RR-5-10 and 2-RR-5-10 Related to Reactor Vessel Inspection Intervals) ML19057A1652019-02-26026 February 2019 NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request ML19057A4212019-02-26026 February 2019 NRR E-mail Capture - Acceptance of Prairie Island Reactor Vessel Capsule Removal Schedule Request ML19008A3562019-01-0707 January 2019 NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Audit Plan Related to the License Amendment Request to Implement 10 CFR 50.69 ML18351A0142018-12-14014 December 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Classification of Certain Fuel Handling Equipment ML18347A3282018-12-12012 December 2018 E-Mail from M. Krick/Sses SSES ISFSI (Conversation Held on December 12, 2018) ML18313A0832018-11-0707 November 2018 NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request ML18235A2982018-08-23023 August 2018 NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request 2024-07-01
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PrairieIslandNPEm Resource From: Eckholt, Gene F. [Gene.Eckholt@xenuclear.com]
Sent: Thursday, April 16, 2009 3:19 PM To: Richard Plasse
Subject:
Draft Turbine Missile Discussion Attachments: Turbine rotor inspection supplement (2).doc 1
Hearing Identifier: Prairie_Island_NonPublic Email Number: 1003 Mail Envelope Properties (7A9B2084CC9CEC45828E829CBF20D638033F6C2C)
Subject:
Draft Turbine Missile Discussion Sent Date: 4/16/2009 3:18:34 PM Received Date: 4/16/2009 3:18:38 PM From: Eckholt, Gene F.
Created By: Gene.Eckholt@xenuclear.com Recipients:
"Richard Plasse" <Richard.Plasse@nrc.gov>
Tracking Status: None Post Office: enex02.ft.nmcco.net Files Size Date & Time MESSAGE 0 4/16/2009 3:18:38 PM Turbine rotor inspection supplement (2).doc 34880 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
DRAFT - FOR INFORMATION ONLY In a letter dated April 6, 2009, NSPM provided its conclusion that the analysis of the probability of damage to safeguard equipment from turbine missiles was not a TLAA. In a conference call on April 15, 2009, the NRC requested clarification about how the Current Licensing Basis (CLB) for turbine missiles addresses the turbine rotor inspection interval. NSPM agreed to provide clarifying information in a supplement to the RAI response.
The CLB for turbine valve testing is encompassed by the PINGP Technical Requirements Manual (TRM), Section 3.7.3, Turbine Overspeed Protection. The TRM is a licensee-controlled document that is maintained consistent with the USAR. A licensee's TRM is recognized by the NRC as an element of a plant's licensing bases in NRR Office Instruction LIC-100, Control of Licensing Bases for Operating Reactors. The TRM requirement for turbine valve stroke testing states, "Frequency of testing shall be consistent with the methodology presented in WCAP-11525, "Probabilistic Evaluation of Reduction in Turbine Valve test Frequency", and in accordance with the established NRC acceptance criteria for the probability of a turbine missile ejection incident of 1.0 x 10-5 per year. In no case shall the turbine valve test interval exceed one year." The NRC approved the use of WCAP-11525 methodology to determine valve test frequency in PINGP License Amendments 86 (Unit 1) and 79 (Unit 2) issued by an NRC letter dated February 7, 1989.
WCAP-11525 was prepared to provide a probabilistic basis for selecting a turbine valve testing interval. The WCAP methodology is used to define a valve test interval that, in conjunction with other factors, maintains the overall probability of turbine missile ejection less than 1E-5/year. The valve test interval, in conjunction with the design configuration and valve failure rates, determines the probability that a design, intermediate or destructive overspeed event could occur. However, the valve test interval, in itself, is only one of the factors which contribute to the overall probability of missile ejection. At PINGP turbine valve stroke tests are currently performed at a nominal interval of six months.
While the CLB does not specifically address a turbine rotor inspection frequency, WCAP-11525 recognizes that the probability of a missile ejection at any speed is a function of the type and condition of the rotor. The probability that a missile would be ejected at normal operating speed or overspeed is directly dependent on the elapsed operating time since the last rotor inspection. Each performance of a rotor inspection reduces the probability of missile ejection from rotor failure.
After each rotor inspection, the probability of a missile ejection from a rotor failure increases with time until the next inspection. Since the purpose of WCAP-11525 was to address the valve testing interval, the conditional probabilities of missile ejection were conservatively assumed values. Even though the overall probability of turbine missile ejection from the fully integral turbine rotor type installed at PINGP could be maintained <1E-5/year with rotor inspection intervals of 30 or more years, the WCAP analysis conservatively assumed a nominal inspection interval of ten operating years. The WCAP analysis did not specify 4/16/09
DRAFT - FOR INFORMATION ONLY this ten operating year interval as a limiting requirement; it was simply one of the variables that had to be specified along with the applicable rotor type as an input to the analysis. At PINGP, turbine rotor inspections are performed at a nominal interval of 100,000 operating hours (approximately 11.4 operating years). Low pressure turbine rotor inspections are currently planned at the next refueling outages (1R26 and 2R26) of both Units 1 and 2. The curve that appears as USAR Figure 12.2-38 is not used to determine a rotor inspection interval.
In summary, in order to satisfy the TRM requirement to maintain the overall probability of turbine missile ejection below 1E-5/year, PINGP must utilize both an appropriate turbine valve test interval and an appropriate turbine rotor inspection interval to assure that the assumptions used in the WCAP-11525 analysis methodology continue to be met. Neither the turbine valve test interval nor the rotor inspection interval involves a time-limited assumption defined by the current operating term of the plant. Therefore, the analysis of the probability of damage to safeguard equipment from turbine missiles is not a TLAA 4/16/09